ORNL/TM-2001/190
Dist. Category UC-407
Life Sciences Division
User's Guide to the DCAL System
K. F. Eckerman
R. W. Leggett
M. Cristy
C. B. Nelson
J. C. Ryman
A. L. Sjoreen
R. C. Ward
Date published: August 2006
Research sponsored by the Office of Radiation and Indoor Air, U.S. Environmental Protection Agency,
Washington DC 20460, under Interagency Agreement 1824-C148-A1, EPA No. DW899934657-3.
Prepared by
OAK RIDGE NATIONAL LABORATORY
P.O. Box 2008
Oak Ridge, Tennessee 37831-6285
managed by
UT-Battelle, LLC
for the
U.S. DEPARTMENT OF ENERGY
under contract DE-AC05-00OR22725
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TABLE OF CONTENTS
TABLE OF CONTENTS i
LIST OF TABLES iv
LIST OF FIGURES v
ABSTRACT 1
1.0 OVERVIEW OF THE DCAL SYSTEM 2
2.0 INSTALLATION 01 DCAL SOFTWARE 5
2.1 BACKGROUND INFORMATION 5
2.2 INSTALLING THE DCAL SYSTEM 5
2.3 INSTALLED FILES 6
2.4 DCAL Main Menu Module 7
3.0 DESIGN OF THE DCAL SYSTEM 8
3.1 INTENDED USERS 8
3.2 FUNCTION AND ORGANIZATION OF DCAL'S MODULES 8
3.3 LIBRARIES OF BIOKINETIC, DOSIMETRIC, AND RISK MODELS OR DATA 11
3.3.1 Library of Biokinetic Models 11
3.3.2 Library of Nuclear Decay Data 12
3.3.3 Library of Data on Specific Absorbed Fractions 12
3.3.4 Library of Risk Models and Mortality Data 12
3.4 DCAL OUTPUT FILES 13
3.5 NAMING CONVENTION FOR SOURCE REGIONS AND BIOKINETIC
COMPARTMENTS 15
3.6 NAMING CONVENTION FOR SYSTEMIC BIOKINETIC FILES AND/; FILES 15
3.7 DCAL'S INI FILE SYSTEM 17
4.0 DCAL'S MAIN MENU 20
4.1 INTERACTIVE MODE 20
5.0 INTERACTIVE IMPLEMENTATION OF DCAL 24
5.1 STEPS IN AN INTERACTIVE RUN OF DCAL 24
5.2 ACTACAL AND SEECAL INI FILES 34
5 .3 INTERACTIVE HOUSEKEEPING PROCEDURE 36
6.0 DCAL's BATCH MODE FACILITY 37
7.0 CREATING ADDITIONAL BIOKINETIC FILES 41
7.1 FORM OF A DEF FILE DESCRIBING A SYSTEMIC BIOKINETIC MODEL 41
7.2 SPECIAL CONSIDERATIONS FOR NAMING COMPARTMENTS USED TO
DESCRIBE CIRCULATION OR EXCRETION OF MATERIAL 42
7.3 FORM OF A GF1 FILE DESCRIBING FRACTIONAL UPTAKE FROM THE
GASTROINTESTINAL TRACT 43
7.4 CREATING DEF or GF1 FILES BY COPYING AND EDITING AN EXISTING FILE 44
8.0 THE METHOD USED BY ACTACAL TO SOLVE BIOKINETIC MODELS 46
8.1 BACKGROUND 46
8.2 DESCRIPTION OF THE METHOD 46
8.3 SOURCES AND SIZES OF ERRORS 48
8.4 SCHEMES FOR SELECTING TIME STEPS 49
8.5 COMPARISONS WITH OTHER SOLVERS 50
8.6 TREATMENT OF DECAY CHAINS OF RADIONUCLIDES 55
8.7 HOW TO CHANGE THE TIME STEPS IN DCAL 56
9.0 HOW DCAL IMPLEMENTS DIFFERENT OPTIONS CONCERNING DECAY
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CHAIN MEMBERS 58
9.1 ASSUMPTIONS USED IN ICRP DOCUMENTS 58
9.2 TECHNICAL OR CONCEPTUAL PROBLEMS THAT MAY ARISE FROM THE
ASSUMPTION OF INDEPENDENT KINETICS OF DECAY CHAIN MEMBERS 59
9.3 HOW DIFFERENT OPTIONS CONCERNING DECAY CHAIN MEMBERS ARE
IMPLEMENTED IN DCAL 60
9.3.1 Implementation of Option 1: Independent Kinetics; User-Predefined Files 60
9.3.2 Implementation of Option 2: The "ICRP-30" Approach 62
9.3.3 Implementation of Option 3: Member-by-Member Default Options 62
10. HOW DCAL ESTIMATES THE RISK OF RADIOGENIC CANCERS 63
10.1 GENERAL CONSIDERATIONS 63
10.2 EXPOSURE SCENARIOS 63
10.3 RISK MODELS USED IN DCAL 64
10.4 Continuity Considerations 66
10.5 Cancer Type and Dose Location Associations 67
11. EXTERNAL DOSE COMPUTATIONAL MODULE 68
11.1 FGR-12 CALCULATIONAL METHODS 68
11.2 ORGAN DOSES FROM MONOENERGETIC ENVIRONMENTAL
PHOTON SOURCES 68
11.3 SKIN DOSES FROM MONOENERGETIC ENVIRONMENTAL ELECTRON SOURCES.. 68
11.4 DOSE COEFFICIENT FORMULATION FOR RADIONUCLIDES 69
11.5 EXTDOSE CALCULATIONS 69
12. DCAL'S UTILITY ROUTINES 72
12.1. UTILITIES INVOKED FROM DCAL MAIN MENU 72
12.1.1 View Work Files - List 72
12.1.2 Plot Selected Data - PLOTEM 72
12.1.3 Tabulate Dose Coefficients - HTAB 73
12.1.4 Nuclide Emissions - RADSUM 74
12.1.5 Decay Chain Details - CHAIN 75
12.1.6 Batch Calculations - DBATCH 76
12.1.7 System Help - HELP 76
12.2 UTILITIES INVOKED BY FUNCTION KEYS 76
12.2.1 Help: Key 76
12.2.2 Active Case: Key 76
12.2.3 =: key 76
12.2.4 =: key 77
12.2.5 About: key 77
12.2.6 ACTINT Utility: Key 77
12.2.7 DRUM Utility: Key 77
12.2.8 BIOTAB Utility: Key 77
12.2.9 EXPORTM Utility: Key 78
12.2.10 DcalSys Utility: I' 10 Key 78
12.2.11 Manual: Key 78
13. SUMMARY AND CONCLUSIONS 79
ACKNOWLEDGEMENTS 80
REFERENCES 81
APPENDIX A ANNOTATED LISTINGS OF DCAL OUTPUT FILES 84
A. 1 File Ru 106AF5.ACT: created by ACTACAL 84
A.2 File Rul06AF5.REQ: created by ACTACAL 85
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A.3 File Rul06HT.SEE: created by SEECAL 86
A.4 File Rul06HT.SEE: created by EPACAL 88
A.5 File Rul06AF5.LOG: created by the DCAL Modules 90
A.6 File Rul06AF5.U50: created by ACTINT32 95
A.7 File Rul06AF5.EUD: created by BIOTAB32 95
A.8 File Rul06AF5.HEF: created by HTAB32 utility 96
A.9 File Rul06AF5.INT: created by the ACTINT32 utility 97
APPENDIX B ANNOTATED LISTINGS OF DCAL BATCH OUTPUT FILES 98
B. 1 i:\AMPIMI.INP File 98
B.2 EXAMPINH.HDB File 98
B.3 EXAMPINH.TAB File 99
B.4 EXAMPINH.RBS File 100
B.4 RSKRSK.RSK File 101
APPENDIX C DCAL LIMITING DIMENSIONS 104
APPENDIX D NUCLEAR DECAY DATA FILES 106
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LIST OF TABLES
Table 4.1. Purposes of modules and utilities available in DCAL main menu 22
Table 4.2. Purposes of the function keys of the DCAL main menu 23
Table 8.1. Comparison of ACTACAL estimates with exact calculations (closed form solution)
of contents of segments of the gastrointestinal tract at times following acute ingestion
of 1 Bq of a very long-lived radionuclide, based on the ICRP's gastrointestinal tract model.... 52
Table 8.2. Comparison of estimates based on our method with exact solutions, applied to a
biokinetic model for iodine (ICRP 1989), assuming intake to blood of an adult
and no radiological deca 53
Table 8.3. Comparison with exact solutions of estimates based on our method, applied to an
age-specific biokinetic model for iodine (ICRP 1989), assuming intake to blood
at age 1 y and no radiological decay 54
Table 8.4. Estimated organ contents (Bq) at different times after injection of americium at age 1 y,
based on the americium model of ICRP Publication 67 (1993) and two
different computational methods3 55
Table 8.5. The DEF file representing the systemic biokinetic model for americium
used in ICRP Publication 67 (1993) 57
Table C.l Restrictions on Compartment Model Definition 104
Table C.2 Restrictions on Decay Chain Definition 104
Table C.3 Restrictions on Emitted Radiations 104
Table C.4 Restrictions within ACTACAL 104
Table C.5 Restriction within SEECAL 105
Table C.6 Restriction within EPACAL 105
Table C.7 Restriction within RISKCAL 105
Table D. 1. Isomers with nonstandard naming convention 108
Table D.2. Structure of data records in NDX file 109
Table D.3. Structure of records in RAD files 110
Table D.4. Structure of records in BET files 110
IV
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LIST OF FIGURES
Fig. 2.1. DCAL's main menu 7
Fig. 3.1. Schematic of the DCAL System 9
Fig. 3.3 Listing of SEECAL.INI file 18
Fig. 4.1. DCAL's main menu 20
Fig. 5.1. Listing of HEF file of age-specific equivalent dose coefficients for ingestion of Sr-90 36
Fig. 6.1. Illustration of a DCAL batch input file 38
Fig. 12.1. DCAL's PLOTEM display 73
Fig. 12.2. RADSUM display from which the radioisotope of interest is selected 74
Fig. 12.3. RADSUM's summary table of the emissions of Pu-241 75
Fig. D-l. Spectrum of beta particles emitted by Kr-87 107
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ABSTRACT
This report serves as a user's manual for the first release of the Dose and Risk Calculation software, DCAL.
DCAL consists of a series of computational modules, driven in either an interactive or a batch mode, for the
computation of dose and risk coefficients. The system includes extensive libraries ofbiokinetic and dosimetric
data and models representing the current state of the art. DCAL has unique capability for addressing intakes of
radionuclides by non-adults. DCAL runs as 32-bit extended DOS and console application under Windows
95/98/NT/2000/XP. It is intended for users familiar with the basic elements of computational radiation
dosimetry. Components of DCAL have been used to prepare EPA Federal Guidance Reports 12 and 13 and a
number of publications of the International Commission on Radiological Protection. The dose and risk values
calculated by this first release are consistent with those published in Federal Guidance Reports 12 and 13.
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1.0 OVERVIEW OF THE DCAL SYSTEM
Under the sponsorship of the U.S. Environmental Protection Agency (EPA), the Dosimetry Research Group
(now the Biosystems Modeling Team in the Advanced Biomedical Science and Technology Group) at Oak
Ridge National Laboratory (ORNL) has developed a comprehensive software system for the calculation of
tissue dose and subsequent health risk from intakes of radionuclides or exposure to radionuclides present in
environmental media. This system serves EPA's current needs in radiation dosimetry and risk analysis. The
Dose and Risk Calculation software, called DCAL, has been used in the development of two federal guidance
reports (Federal Guidance Reports 12 and 13) (EPA 1993, 1999) and several publications of the International
Commission on Radiological Protection (ICRP), specifically in the computation of age-specific dose
coefficients for members of the public (ICRP 1989, 1993, 1995a, 1995b, 1996).
DCAL is designed for use on a personal computer (PC) or scientific work station by users with experience in
scientific computing and computational radiation dosimetry. The system consists of a series of computational
modules driven by a user interface. DCAL may be used either in an interactive mode designed for evaluation of
a specified exposure case or in a batch mode that allows non-interactive, multiple-case calculations on a PC or
scientific work-station. Only the PC version of DCAL is being distributed.
DCAL performs biokinetic and dosimetric calculations for the case of acute intake of a radionuclide by
inhalation, ingestion, or injection into blood at a user-specified age at intake. The user may compute either
equivalent or absorbed (low and high LET) dose rates as a function of time following intake of the radionuclide.
The equivalent dose option enables the generation of a table of age-specific dose coefficients, i.e., committed
equivalent doses to organs and committed effective doses per unit intake, such as those published in the ICRP
documents on doses to the public from intake of radionuclides (ICRP 1989, 1993, 1995a, 1995b, 1996).
If the endpoint the calculation is radiogenic risk, the absorbed dose option must be selected because the
radiation risk factors used by DCAL are expressed in terms of absorbed dose. To calculate radiogenic risk,
DCAL couples the generated absorbed dose rates with radiation risk factors and mortality data to predict organ-
specific risk of radiogenic cancer death from chronic intake of a radionuclide.
DCAL includes a module for the evaluation of dose rate resulting from external exposure to radionuclides
present outside the body in environmental media, i.e., distributed in an airborne cloud, in water, on the ground
surface, or to various depths in the soil. That module uses the photon and electron dosimetric data tabulated in
Federal Guidance Report 12 (EPA 1993) to generate radionuclide-specific dose rate coefficients. As is the case
for intake of radionuclides, if the endpoint of the calculation is radiogenic risk, DCAL couples the generated
absorbed dose rates with radiation risk factors and mortality data to predict organ-specific risk of radiogenic
cancer death from chronic exposure to the radionuclide in the environmental medium. The discussion below
focuses on the dose from internally deposited radionuclides. The reader is referred to Chapter 11 for further
discussion of the external dose computations.
For the case of radionuclide intake at a pre-adult age, anatomic and dosimetric parameter values are interpolated
in a continuous manner throughout the period of growth. If age dependence is indicated in the biokinetic model,
the biokinetic parameter values also are interpolated in a continuous manner throughout growth or throughout
life. Age-specific biokinetic models for several radioelements are provided in the ICRP's series on doses to
members of the public from intake of radionuclides. The age at intake considered in that series are 100 d, 1 y,
5 y, 10 y, 15 y, and adult. In the ICRP documents as well as in DCAL, biokinetic parameter values for
intermediate ages are based on linear interpolation with age. The beginning age of adulthood is defined in the
element-specific systemic biokinetic model. That age is 20 y for most elements but is 25 for some bone-seeking
elements because of substantial changes in the modeled biokinetics of the element between ages 20 and 25 y.
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The dosimetric calculations proceed in three main steps:
Step 1: calculation of time-dependent activity of the parent radionuclide and its radioactive progeny
present in anatomical regions (source regions) of the body;
Step 2: calculation of SEE values for all combinations of source region S and target region T, where
SEE(T,S) is the dose rate in T per unit activity present in S;
Step 3: calculation of dose rates or equivalent dose rates, based on output generated in Steps 1 and 2.
Dose coefficients may be computed after Step 3. A dose coefficient is an integrated organ dose or dose
equivalent, or an effective dose per unit activity intake. The integration period is 50 y for intake by the adult
and from age at intake to age 70 y for intake at a pre-adult age.
Cancer risk coefficients can also be calculated after completion of Step 3 provided the absorbed dose option has
been selected. For a given radionuclide and exposure mode, both a mortality risk coefficient and a morbidity
risk coefficient are calculated. The mortality risk coefficient is an estimate of the risk, per unit activity inhaled
or ingested for internal exposures or per unit time-integrated activity concentration in air or soil for external
exposures, of dying from a radiogenic cancer. The morbidity risk coefficient is a comparable estimate of the
average total risk of experiencing a radiogenic cancer, whether or not the cancer is fatal. Either risk coefficient
applies to an average member of the public, in the sense that estimates of risk are averaged over the age and
gender distributions of a hypothetical closed "stationary" population whose survival functions and cancer
mortality rates are based on recent data for the U.S. The method of calculation of the risk coefficients is
described in Chapter 10.
In its calculations of dose and risk, DCAL relies on data libraries defining the biokinetic models, nuclear decay
data, anatomic data, radiation risk models, survival data, cancer mortality and morbidity, and various other
miscellaneous data. These libraries enable the user to compute state-of-the-art estimates of radiation dose and
risk from intakes of or exposure to radionuclides, with minimal input.
DCAL is designed to allow easy expansion of its library of systemic biokinetic models and gastrointestinal
uptake values (f\ values) with user-supplied models. Such expansions must adhere to DCAL's design
considerations. The biokinetic, dosimetric, and risk libraries are considered as permanent files of the DCAL
System, although virtually all portions of these libraries are readily accessible and could be modified by users
who are familiar with these data and who have acquire an understanding of the organization and structure of the
DCAL system.
Two sets of systemic biokinetic models are contained in the DCAL libraries: the models for occupational
exposure recommended in ICRP Publication 68 (1994b); and the age-specific models applied in the production
ofEPA's Federal Guidance Report 13. The latter set of models is generally the same as that used in the ICRP's
series of documents on doses to members of the public, as summarized in ICRP Publication 72 (1996), although
a few of the ICRP's models were modified as described in Federal Guidance Report 13. The biokinetic libraries
include: the latest ICRP model of the respiratory tract as described in ICRP Publication 66 (1994a); the ICRP's
gastrointestinal tract model used in calculations for Federal Guidance Report 13 (the GI model first used in
ICRP Publication 30, 1979); and the urinary bladder voiding model described in ICRP Publication 67 (1993).
The nuclear decay library contains nuclear decay data currently used by the ICRP and the Medical Internal
Radiation Dose (MIRD) Committee of the Society of Nuclear Medicine (Weber etal. 1989) and information on
the energies and intensities of the radiations associated with spontaneous nuclear transformation of 838
radionuclides. The photon specific absorbed fraction library is based on the data of Cristy and Eckerman (1987,
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1993) as currently used by the ICRP. Organ masses for adults are taken from ICRP Publication 23 (Reference
Man, ICRP 1975) and, for children, the values are taken from the phantoms of Cristy and Eckerman (1987,
1993), which are based on data from ICRP Publication 23. The radiation risk models are based on the EPA's
current methodology (EPA 1994), but some parameter values of those models have been modified as described
in Federal Guidance Report 13 (EPA 1999). Gender-specific survival data are from the U. S. Decennial Life
Tables for 1989-1991 (NCHS 1997).
Due to a recent movement in radiation protection toward biological realism in the treatment of radionuclides in
the body, some of the biokinetic models currently used by the ICRP, and included in the DCAL libraries, are
considerably more complex than models traditionally used by the ICRP. For example, some systemic biokinetic
models depict continual redistribution of activity among 20 or more compartments at rates that vary with age.
The ICRP's current age-specific respiratory tract model (ICRP Publication 66, 1994a) is of similar size and
complexity. In the ICRP documents on doses to the public from intake of radionuclides, the systemic models
are sometimes used in conjunction with the assumption of independent kinetics of radioactive progeny, which
requires the tracking of individual chain members produced in the body by radioactive decay of the parent.
With such models and assumptions, determination of the time-dependent distribution of all chain members may
require the solution of a first-order model involving (in effect) several hundred compartments, feedback of
activity between compartments, and transfer rates that vary with age and hence time. The corresponding set of
coupled differential equations often is too large and complicated to be solved by most conventional solvers, and
solution by any conventional solver requires enormous computing space and time.
Rapid solution of these complex models by DCAL with the relatively modest CPUs available on PCs is
accomplished by applying an efficient approximation technique developed by the dosimetry team. The
technique has no restrictions of practical importance on the number of compartments, the network of flows
between compartments, the number of radioactive daughter products, or the paths of movement of chain
members. The technique is unconventional in that the problem of solving the model is not viewed as one of
solving a set of coupled differential equations representing the model. Instead, the model is viewed as a series of
compartments and the time period of interest as a series of time steps, and the contents of each compartment on
each time step is approximated as the closed-form solution of a particularly simple linear differential equation.
Any specified level of accuracy can be achieved by selecting time steps sufficiently small. For the biokinetic
models included in the DCAL libraries, the set of default time steps used in DCAL typically yields relative
errors of at most a few tenths of one percent with regard to instantaneous activities in compartments and
virtually exact integrated activities. For a specified level of accuracy, computing time and storage requirements
increase roughly in proportion to the number of compartments in the model but with current (2006) PCs is at
most a few seconds even for the most complex models considered in Federal Guidance Report 13, for example.
The approximation technique is described in detail in Section 8.
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2.0 INSTALLATION OF DCAL SOFTWARE
2.1 BACKGROUND INFORMATION
DCAL is designed for use on a personal computer (PC) or scientific work station by users with experience in
scientific computing and computational radiation dosimetry. The system consists of a series of computational
modules driven by a user interface. DCAL may be used either in an interactive mode designed for evaluation of
a specified exposure case or in a batch mode that allows non-interactive, multiple-case calculations.
The DCAL system operates as a 32-bit console application on Pentium-class PC with Windows
95/98/NT/2000/XP operating systems. The installation requires about 30 Mbytes of space on the hard drive.
Additional space is necessary for files generated during use of DCAL, with the total required space depending
on the user's housekeeping practices.
A conventional Windows installation procedure is provided to install the DCAL system. The procedure installs
the following three components of the DCAL system:
• computational and utility modules;
• dosimetric data libraries;
• biokinetic data libraries.
The installation procedure creates a folder (or directory) on the hard drive with the default name DCAL within
which all subsequent folders and files are installed. Although the installation procedure allows the user to
install the software into a folder of his/her choice, it is recommended that DCAL's main folder not be under
another folder, such as C:\Program Files. DCAL's data libraries and the computational modules must reside in a
folder off the main folder, and the names of these folders cannot be changed.
2.2 INSTALLING THE DCAL SYSTEM
From Windows Explorer click on the DCAL setup executable (DCAL_setup.exe), or from Start\Run enter
d: \dcal_setup, where d: is the drive with the distribution copy of DCAL. Follow the installer's instructions to
complete the installation. Following completion of the installation the user should view the "readme.txt" file for
any information that may have been added after this document was prepared. The installation procedure places a
shortcut on the desktop that can be used to invoke DCAL. DCAL's computational modules use ANSI device
drivers to control the position of the cursor on the screen. If these drivers (ANSI.SYS) are not installed, various
strange characters will appear and scroll by on the screen during the computations. Use the Windows FIND
utility (Start\Find) to locate the file ANSI.SYS on the PC; typically it is present in the
WINDOWS\COMMAND folder. On Windows 95/98 systems it is necessary to use an ASCII editor (or
Windows NotePad) to modify the CONFIG.SYS file located in the root of drive C: to include
DEVICE=C:\WINDOWS\HIMEM.SYS
DOS=HIGH, UMB
DEVICEHIGH=C:\WINDOWS\COMMAND\ANSI.SYS
On Windows NT/2000/XP machines the CONFIG.NT file should include
DEVICE=%SystemRoot%\SYSTEM32\HIMEM.SYS
DOS=HIGH, UMB
DEVICE=%SystemRoot%\SYSTEM32\ANSI.SYS
The user should confirm the location of HIMEM.SYS and ANSI.SYS on these systems.
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Windows ME does not support the ANSI device drivers, i.e., the CONFIG.SYS file. Windows ME users can
download the utility ANSI.COM from www.pcmag.com/article2/0,1759,155622 l,OO.asp. Users must add the
line ANSI.COM > null to the file C:\Windows\Command\CMDINIT.BAT. This BAT files is automatically
executed by Windows ME each time a console or DOS application is run.
DCAL's computational modules are written in FORTRAN and compiled as 32-bit extended DOS applications
using the Open WATCOM1 compiler with the PMODE/W DOS extender. The interactive interface module and
the various utilities are 32-bit console applications compiled with PowerBasic's Console Compiler2. DCAL will
not run under DOS 6.2 or Windows 3.1 because of the 32-bit codes.
2.3 INSTALLED FILES
The user should consult the README.TXT file in the DCAL folder for any updated information on the DCAL
System that may have been added after this document was prepared. The file DCALFILE.TXT in the DCAL
folder lists all the files that were installed with their size and date/time stamp. The following is a summary of
the locations and numbers of installed files.
Folder: C:\DCAL contains 4 files
Folder: C:\DCAL\BIN contains 23 files
Folder: C:\DCAL\INI contains 8 files
Folder: C:\DCAL\MAN contains 1 files
Folder: C:\DCAL\HLP contains 8 files
Folder: C:\DCAL\DAT\NUC contains 3 files
Folder: C:\DCAL\DAT\SAF contains 23 files
Folder: C:\DCAL\DAT\EXT contains 22 files
Folder: C:\DCAL\DAT\MIS contains 27 files
Folder: C:\DCAL\DAT\RSK contains 8 files
Folder: C:\DCAL\DAT\BIO\l68 contains 281 files
Folder: C:\DCAL\DAT\BIO\F13 contains 333 files
The DCAL utility, DCALSYS, invoked from System Help on the DCAL Main Menu (see Sect 2.4), will
generate a corresponding snapshot of the files currently residing in the DCAL System. That utility can be run at
any time to create a file named DCALSYS.DAT that can be compared to DCALFILE.TXT in the root folderto
verify the integrity of the system.
1 Open Watcom is an effort of the Open Source development community to maintain and enhance the Watcom C/C++
and Fortran compilers. See http://www.openwatcom.org/ for further information.
2 PowerBASIC, Inc.; 1978 Tamiami Trail S. #200; Venice, FL 34293. See http://www.powerbasic.com/ for further
information.
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2.4
DCAL Main Menu Module
All DCAL computations are invoked from DCAL's Main Menu, shown in Fig. 2.1. The install procedure places
a shortcut for this module on the desktop. Clicking on the shortcut invokes the module DCAL2005 .EXE, which
is present in the folder DCAL.
DCAL Main Menu Ver 8.3 June 26,2006
Dose and Risk Calculation System
Uer. 8.3 6-26-06
U.S. Environmental Protection Agency
SEE Calculations
Dose Coefficients
Risk Coefficients
EECAL
PACAL
ISKCAL
External Dose Cals - E TDOSE
«««<««<«« UTILITIES »»»»»»»»
Uieu Work Files - 1ST
Plot Selected Data - LOTEM
Tabulate Dose Coeff- H AB
RA SUM
Decay Chain Details- hain
Batch Calculations - D ATCH
ELP
Nuclide Emissions
ctivity as f
Compute activity us. time in compartments; to obtain U_50 Cnt/Bq>.
=Help =Actiue Case =..SbioSf13 =..SwrkSfgr!3 =About
Fig. 2.1. DCAL's main menu.
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3.0 DESIGN OF THE DCAL SYSTEM
3.1 INTENDED USERS
DCAL is a menu-driven scientific software system designed for users who have experience in scientific
computing and a working knowledge of computational radiation dosimetry. The discussions in this user's guide
assume fundamental knowledge in:
• computer programming;
• compartmental modeling;
• radiation physics.
3.2 FUNCTION AND ORGANIZATION OF DCAL'S MODULES
DCAL consists of a series of computational modules driven by the interactive-menu interface shown in Fig. 2.1.
A schematic of the DCAL system is shown in Fig. 3.1.
The dosimetric calculations for intake of a radionuclide proceed in three main steps:
Step 1: Activity module (ACTACAL): calculation of time-dependent activity of the parent radionuclide
and its radioactive progeny present in anatomical regions (source regions) of the body;
Step 2: SEE module (SEECAL): calculation of SEE values for all combinations of source region S and
target region T, where SEE(T,S) is the dose rate in T per unit activity present in S;
Step 3: Dose rate module (EPACAL): calculation of dose rates or equivalent dose rates, based on output
generated in Steps 1 and 2.
If the absorbed dose option has been selected, risk calculations can then be undertaken after completion of
Step 3. Risk calculations are carried out by the RISKCAL module and, in the case of inhalation or ingestion,
are based on an assumed intake of 1 Bq of the parent radionuclide per day, throughout life. The calculations are
based on best available age-specific risk coefficients and mortality data.
If the equivalent dose option has been selected, then dose coefficients may be calculated after completion of
Step 3. Dose coefficients include integrated organ dose equivalents as well as the effective dose per unit intake.
Dose coefficients are derived by integrating the equivalent dose rates generated in Step 3. The integration is
performed by fitting a spline function to the equivalent dose rates and then evaluating the exact integral of the
function. The spline-fitting method used in DCAL does not exhibit the undesirable oscillations between
adjacent points that often occur with spline fits (de Boor 1978, Fritsch and Carlson 1980, Fritsch and Butland
1982).
In its calculations of dose and risk, DCAL relies on libraries of biokinetic and dosimetric models, nuclear decay
data, anatomic data, radiation risk models, survival data, cancer mortality and morbidity data, and other
miscellaneous data. These libraries of state-of-the-art models and data allow best available estimates of dose
and risk from internally deposited radionuclides, with minimal input by the user. As described later, DCAL
allows expansion of portions of its library of biokinetic data with user-supplied files.
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DCAL System Schematic
c
Bio kinetic
Models
Nuclear Decay
Data
ACTACAL
EPACAL
DOSE
RATE
FILE
c
Anatomical
Parameters
Absorbed
Fraction Data
SEECAL
RISKCAL
RISK
FILE
f Risk I
I Models I
f U.S. Vital I
I Statistics I
Fig. 3.1. Schematic of the DCAL System
Calculations performed using DCAL inherit a pedigree from the computational modules and the various
permanent data files (libraries) used in the calculations. All computational modules access the appropriate
libraries for their common information needs. For example, ACTACAL and SEECAL both call upon the same
data libraries for the numerical values of organ masses and the energies of emitted radiations. This adds a level
of assurance to the computations and minimizes the information requested of the user. For example, the half-
life of the radionuclide taken into the body and a description of subsequent radioactive decay chain, if any, are
obtained from the library rather than from user input.
When DCAL is installed on a PC, the folder DCAL (or user-selected name) is created, along with several
folders that contain executable files, permanent data files, system help files, and output files generated by the
user. The locations of different types of files within the DCAL folder are indicated in Fig. 3.2.
9
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DCAL
I
| bin (contains all executable files)
I
| dat (contains all permanent data files)
I I
| | bio (systemic biokinetics and f± values)
I I I
| | | i68 (from ICRP Publication 68)
I I I
| | | fl3 (files used in Federal Guidance 13)
I I I
| | 1 usr (user-supplied)
I I
| | ext (external dose files of Federal Guidance 12)
I I
| | mis (miscellaneous data files)
I I
| | nuc (nuclear decay data files)
I I
| | rsk (health risk coefficient files)
I I
| 1 saf (specific absorbed fraction data files)
I
| hip (deal system help files)
I
| pdf (user manual pdf)
I
1 wrk (subdirectories into which output is directed)
I
| fgrl3
I
| work
I
1 work2
Fig. 3.2 Organization of DCAL files by folder. Names of folders off the main folder not be changed.
The folder DCAL contains the executable file DCAL2005.exe that serves as the Main Menu for the DCAL
System. All other executable files (* .exe) of the system are located in the folder BIN and are thus isolated from
other files as a housekeeping aid. The folder HLP contains system help files that can be accessed from the
DCAL Main Menu.
Permanent data files are contained in folders that branch from the folder \DCAL\DAT. Two of the folders,
\DCAL\DAT\EXT and \DCAL\DAT\RSK, contain permanent data files used in risk computations. The other
folders off \DCAL\DAT contain files representing biokinetic and dosimetric models or data.
10
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3.3
LIBRARIES OF BIOKINETIC, DOSIMETRIC, AND RISK MODELS OR DATA
3.3.1 Library of Biokinetic Models
With exceptions described below, the biokinetic files included in the DCAL library represent biokinetic models
recommended in recent publications of the ICRP. The following biokinetic models are available:
• Respiratory tract kinetics:
o model of ICRP Publication 66 (1994a).
• Transfer kinetics through segments of the gastrointestinal (GI) tract:
o model of ICRP Publication 30 (1979).
• Clearance from urinary bladder contents via urinary excretion:
o urinary bladder voiding model described in ICRP Publication 67 (1993).
• Systemic biokinetics and GI absorption fraction (/i value):
o biokinetic models and f values from ICRP Publication 68 (1994b);
o biokinetic models and f values used in Federal Guidance Report 13 (EPA 1999).
With a few exceptions, the biokinetic models and f values used in Federal Guidance Report 13 (EPA 1999) are
the same as those used in ICRP Publication 72 (1996), which is a compilation of age-dependent dose
coefficients for members of the public. The exceptional cases are as follows: the systemic biokinetic models for
radioisotopes of actinium and protactinium are updates of models recommended by the ICRP; multiple f) values
for chromium are given in ICRP Publication 72, but only the value that applies to hexavalent chromium is used
for ingestion cases in Federal Guidance Report 13; and the fj value for polonium used in ICRP Publication 72
(0.5) is applied to polonium in diet, but a smaller value (0.1) is applied to polonium in tap water. The files in
folder \DCAL\DAT\BIO\I68 represent the systemic biokinetic models recommended in ICRP Publication 68
(1994b) on occupational exposures. The files in folder \DCALYDAT\BIOYF 13 represent the systemic biokinetic
models used in Federal Guidance Report 13 (EPA 1999).
The DCAL system is designed to accept user-supplied systemic biokinetic models andf values for elements but
is not designed to allow expansion of the libraries containing respiratory, gastrointestinal, or urinary bladder
voiding models.
Biokinetic data other than the systemic biokinetics and f) values are contained in the folder
\DCAL\DAT\BIO\MIS. For example, this folder contains files of transfer rates required to implement the
respiratory tract model of ICRP Publication 66 (1994a).
The biokinetic files are read by the ACTACAL module. This calculates activity as a function of time in the
compartments specified in the biokinetic data files.
11
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3.3.2 Library of Nuclear Decay Data
Information on the energies and intensities of the various radiations emitted by 83 8 radionuclides are contained
in the file ICRP38.RAD found in the folder \DCAL\DAT\NUC. This includes 825 radionuclides whose decay
data were evaluated during the preparation of ICRP Publications 30 and 38 (ICRP 1983) and 13 additional
radionuclides whose decay data were evaluated more recently by the Medical Internal Radiation Dose (MIRD)
Committee of the Society of Nuclear Medicine (Weber et al. 1989). Abridged tabulations of these data have
been published by the ICRP in Publication 38 (1983). The index file ICRP38.NDX contains pointers to the
initial record of each radionuclide in the RAD file and other data, such as the half-life and fraction of the
nuclear transformation forming a radioactive daughter nucleus. The file ICRP3 8 .BET contains the beta spectra
for beta emitters.
3.3.3 Library of Data on Specific Absorbed Fractions
Age-dependent SEE values are used to convert the time-dependent distribution of activity in the body, as
predicted by a biokinetic model, to absorbed dose rates or equivalent dose rates to organs. For a given target
organ T and a given source organ S, the quantity SEE(T,S) reflects the yield and average energy (and, for
calculation of equivalent dose rates, a radiation weighting factor) for each type of radiation emitted from S as
well as the specific absorbed fraction SAF(T, S) for that radiation type. SAF(T, S) is the fraction of emitted energy
from source organ S that is absorbed by target organ T, per unit mass of T.
For the parent radionuclide and each decay chain member considered in the ACTACAL calculation, the
SEECAL module calculates age-dependent SEE values for each source and target organ pair indicated in the
SEECAL request file generated by ACTACAL. These SEE calculations are based on (1) nuclear decay data
contained in the file ICRP3 8 .RAD in the folder \DCAL\DAT\NUC; (2) a library of specific absorbed fractions
for non-penetrating radiations contained in folder \DCAL\DAT\SAF; (3) a library of specific absorbed fractions
for photons contained in folder \DCAL\DAT\SAF; and (4) age-specific organ masses contained in folder
\DCAL\DAT\SAF. The specific absorbed fractions are those currently used by the ICRP (Cristy and Eckerman
1987, 1993). Organ masses for adults are taken from ICRP Publication 23 (1975) (Reference Man). For
children, age-specific organ masses are taken from the phantoms of Cristy and Eckerman (1987), which are
based on data from ICRP Publication 23.
3.3.4 Library of Risk Models and Mortality Data
Radiogenic cancer risk models are used to convert estimates of radiation dose to estimates of excess force of
mortality attributable to that dose. The risk calculations performed by DCAL are for attributable risk.
Attributable risk is defined as the likelihood (according to the risk model) of death from cancer or development
of cancer due to a radiation exposure.
The radiation risk models used in DCAL are based on the U.S. EPA's radiation risk methodology (EPA 1994)
but have been updated in some cases as described in Federal Guidance Report 13 (EPA, 1999). The EPA's risk
models are embodied in libraries of age- and gender-specific risk coefficients, survival data, and force of
mortality data for specific cancers. These libraries are found in the folder \DCAL\DAT\RSK.
The risk coefficients used in DCAL are age specific and for most sites represent compromise values based on
different but equally plausible methods of transporting risk across populations (EPA 1994; EPA 1999). Gender-
specific survival data are from the U. S. Decennial Life Tables for 1989-1991 (NCHS 1997). Mortality data are
from 1989-1991 vital statistics mortality data (NCHS 1992, 1993a, 1993b).
12
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3.4 DCAL OUTPUT FILES
Each computational module of DCAL generates several output files, with the precise number of files depending
on the options selected during the interactive session. The output files are "self-documenting" in the sense that
they contain information that identifies input data files, such as names, dates of creation, and file size. This
information defines the pedigree of the results. In addition, each module generates, or contributes to, a log file
(extension LOG) that records general information concerning the input data sets (e.g., name and date when
created), plus relatively detailed information on the decay chain, source and target organs, biokinetic
compartments, biokinetic parameter values, and organ masses. The user can request that ACTACAL generate an
output file (extension CPT) of the time-dependent activities in all compartments in the model, in addition to the
standard file of activities within the source regions of the model. Other DCAL modules are not affected by
ACTACAL's option to generate the CPT file.
The names of all DCAL files follow the 8.3 DOS file name convention, that is, long file names are not
permitted. With the exception of files of SEE values, a DCAL output file is assigned a name of the form
XXZZZUVW.[extension], where:
The first five characters (XXZZZ) are formed from the radionuclide name (e.g., H-3, Ra-226,
Am-244m, etc.). If the nuclide name contains more than six characters, then the dash and the
least significant digit in the mass number are not used; for example, the characters AM44M
represent Am-244m. If the nuclide name involves six characters then the dash is deleted, for
example RA226 denotes Ra-226. For names of length five or less the full name is retained with
the underscore character used to fill in any unused positions. For example, H-3 , C-14_, and I-
131 appear in the name of the files associated with intakes of H-3, C-14, and 1-131, respectively.
The sixth position (U) is a letter that identifies the age at intake, w ith A being the youngest age, B
the next age, and so forth. If only one age at intake is considered, e.g., the adult, the identifying
letter is A. If the intake ages considered are those of the ICRP's series on doses to members of
the public, they are identified as follows:
A = infant (100 d)
B = age 1 y (365 d)
C = age 5 y (1825 d)
D = age 10 y (3650 d)
E = age 15 y (5475 d)
F = adult; age 20y (7300 d) or 25 y (9125 d) (for certain bone
seekers)
The seventh position (V) in the file name identifies the intake mode. G and J denote intakes by
ingestion and injection into blood, respectively. Inhalation intakes are noted by the absorption
type assigned to the aerosol, i.e., absorption type F, M, or S of the ICRP Publication 66 (1994a)
model. For inhalation of vapor or gases the seventh and eighth places are assigned the letters AG.
The eighth position (W) identifies the size of the inhaled aerosol (e.g., 5 for an activity median
aerodynamic diameter or AMAD of 5 |_im) and contains the underscore character for the other
intake modes. If the particle size is not an integer then W may not be unique and meaningful.
Specific file extensions are used to identify different types of output. For intake case XXZZZUVW, some or all
of the following files are generated, depending on the options selected during the interactive session:
XXZZZUVW.LOG, created by the ACTACAL module, with contributions from other modules,
13
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is a master log file containing general identifying information on all data files used in the
calculation and relatively detailed information on decay chains, source and target organs,
biokinetic compartments, biokinetic parameter values, and organ masses.
XXZZZUVW.ACT, created by ACTACAL, is the file of age- and time-dependent activities of
parent and decay chain members in source organs;
XXZZZUVW.CPT, created by ACTACAL if requested by the user, contains age- and time-
dependent activities of parent and decay chain members in each compartment of the biokinetic
model;
XXZZZUVW.REQ, created by ACTACAL, contains the information needed by the SEECAL
module to generate the necessary SEE values (e.g., parent and decay chain members, age(s) at
intake, and source and target regions);
XXZZZUVW.DRT or XXZZZUVW.HRT, created by the EPACAL module, is the file of
absorbed or equivalent dose rates, respectively, depending on the user's selected option;
XXZZZUVW.HEF, created by HTAB utility, is a table of age-specific dose coefficients
(committed equivalent doses and effective doses per unit intake), similar to tables given in the
ICRP's series on doses to members of the public. If the absorbed dose option is selected, then the
low and high LET absorbed dose committed organ doses will be tabulated.
XXZZZUVW.RSK, created by RISKCAL module, records the gender-specific cancer risk, by
cancer site, resulting from unit intake of a radionuclide at each age (0 y, 1 y, 2 y, ...)
XXZZZUVW.RBS, created by RISKCAL module, records gender-specific estimates of mortality
and morbidity risk by cancer site for activity intakes during age intervals, including lifetime
intake. The calculation assumes intake (by the user-specified intake mode) of 1 Bq of the parent
radionuclide per day throughout an indicated age range.
SEE files have a name of the form [parent]DL. SEE or [parent]HT.SEE, where
[parent] is the abbreviation, without hyphens or underscores, of the parent radionuclide (e.g.,
CI4, CA45, or RA226);
DL indicates that the radiation weighting factor has not been applied (i.e., the SEEs are for
absorbed dose calculations);
HT indicates that radiation weighting factors have been applied (i.e., the SEEs are for dose
equivalent calculations).
14
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3.5 NAMING CONVENTION FOR SOURCE REGIONS AND BIOKINETIC
COMPARTMENTS
For purposes of computing radiation dose it is necessary to relate the compartments of the biokinetic model to
anatomical regions of the body referred to as source regions. To allow DCAL to identify source regions on the
basis of the names of the biokinetic compartments, a standard naming convention for source regions and
biokinetic compartments has been adopted. This naming convention also has the advantages of facilitating
quality assurance and of allowing ACTACAL to assemble biokinetic information in a consistent manner from a
variety of permanent and temporary files.
A list of standard names of source regions is provided in Table 3.1. Names shown in bold are "reserved names"
since they are used explicitly within some of the computational modules. All other names are fixed in the
STDNAMES.TXT file in the folder \DCAL\DAT\MIS.
The name of a compartment of a biokinetic model must be an extension of the standard name of the source
region. For example, if the biokinetic model includes liver as a separate compartment, then the name of this
compartment could be simply "Liver" or could be of the form "Liver_X", where the symbol "_X" represents, in
effect, a subscript. The underscore character must be present if a subscript is used. If the biokinetic model
includes multiple liver compartments, then the name of each compartment must be of the form "Liver_X"
except that one of the compartments could be named "Liver", with no subscript. As an illustration, if three
compartments are used to represent the biokinetics of the material in the liver, then some possible names for
these compartments are: (1) Liver_l, Liver_2, Liver_3; (2) Liver, Liver_l, Liver_2; (3) Liver_a, Liver_b,
Liver_c; (4) Liver_l, Liver_a, Liver_b.
The name of the compartment representing the circulation (called the transfer compartment in some ICRP
publications) must be of the form "Blood" or "BloodX". At least one "Blood" compartment must be included
in the data files describing the biokinetics of systemic material. Systemic material destined for urinary excretion
should be transferred to a compartment named "UBCont" if a dose estimate for the urinary bladder (UB) is to
be made. Similarly, systemic material destined for fecal excretion should be transferred to either the "SI_Cont"
or "ULI_Cont" compartment of the gastrointestinal tract (transfer to "SI_Cont" allows some reabsorption to
blood as determined by the f value). If the biokinetic model indicates that material is simply lost from the
systemic circulation without specifying an excretion route, as in many of the older ICRP models, or if the
specified route of excretion is different from urine and feces (e.g, hair or sweat), then the transfer should be
specified to a compartment labeled "Excreta". The compartments named "Excreta", "Urine", and "Feces" are
outside the body and excluded from the dosimetric calculations.
3.6 NAMING CONVENTION FOR SYSTEMIC BIOKINETIC FILES AND/7 FILES
DCAL locates its input data by searching for standard file names. In the case of element specific files, DCAL
extracts the symbol of the element from the name of the radionuclide and forms a file name using specific file
extensions. The extensions for systemic biokinetic files and f] files are DEF and GF1, respectively. With some
exceptions described in the following paragraphs, the name of the systemic biokinetic file for the parent
radionuclide will have the form X.DEF or XX.DEF, where X or XX is the chemical symbol of the element.
With exceptions described below, the name of the f) file will have the form X.GF 1 or XX.GF 1, where X or XX
is the abbreviation of the element. For example: the systemic biokinetic file for radium generally will have the
name RA.DEF; the systemic biokinetic file for iodine will have the name I.DEF; and the f] file for americium
will have the name AM.GF1.
15
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Table 3.1. Standard names of source regions used in DCALa
Systemic
Lung
GI-Tract
Excretion
Adrenals
Lung Cont
St Cont
UB Cont
UB Wall
ET1-sur
SI Cont
Urine
C Bone-S
ET2-sur
ULI Cont
Feces
C Bone-V
ET2 bnd
LLI Cont
Excreta
T Bone-S
ET2-seq
T Bone-V
LN-ET
Brain
BB1-gel
Breasts
BB1-sol
St Wall
BBi-bnd
SI Wall
BB1-seq
ULI Wall
bbe-gel
LLI Wall
bbe-sol
Kidneys
bbe-bnd
Liver
bbe-seq
Lng Tiss
AI
Muscle
LN-Th
Ovaries
NP Cont
Pancreas
TB Cont
Skin
P Cont
Spleen
LN Lung
Testes
Thymus
Thyroid
GB Cont
GB Wall
Ht Cont
Ht Wall
Uterus
Body Tis
Blood
BT-Soft
Other
aNames shown in bold italics have special meaning within the DCAL system in that
they may appear in kinetic files that are linked. Abbreviations: Cont = contents,
GB = gallbladder, LLI = lower large intestine, ULI = upper large intestine, SI =
small intestine, St = stomach, Ht = heart, Lng = lung; R = red,
C = cortical, T = trabecular, S = surface, V = volume, ¥ = whole, WB = whole-body,
UB = urinary bladder.
In some cases, different chemical forms of a radionuclide are assigned different biokinetic models and hence are
defined in different DEF files. In such cases, special root names must be given to the various DEF files for the
radionuclide. These special names are listed in a file called $BIODEF.DAT in the appropriate biokinetic folder.
For example, in ICRP Publication 67 (1993), different biokinetic models are used for organic and inorganic
sulfur. The biokinetic folder \DCAL\DAT\BIO\FGR13 contains the file S ORG.DEF representing organic
sulfur and the file S INORG.DEF for inorganic sulfur, and these files are defined in the file $BIODEF.DAT. In
the interactive mode, DCAL checks the file $BIODEF.DAT to determine whether special file names are listed
for the radionuclide under consideration. If special file names are present, then a prompt is issued to the user to
select the appropriate file. For batch runs, the special files must be assigned in the batch input file (see Chapter
6.0).
16
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There are also cases in which different isotopes of an element are assigned different biokinetic models and
hence different DEF files. In the ICRP's series of publications on doses members of the public (ICRP 1989,
1993, 1995a, 1995b, 1996), the simplifying assumption is made that the decays in bone of some short-lived
isotopes of bone seeking elements (usually but not always isotopes with half-life no greater than 15 d) occur on
bone surfaces and decays of the long-lived isotopes occur in bone volume. Thus, separate biokinetic files are
needed for short- and long-lived isotopes of these elements, because different sources regions within bone are
considered in the two cases. A name of the form X_SUR.DEF or XX_SUR.DEF is assigned to the file for short-
lived isotopes (where X or XX is the chemical symbol of the element) and a name of the form X_VOL.DEF or
XX_VOL.DEF is assigned to the file for long-lived isotopes. Directions for assigning a given biokinetic file to
a given isotope (i.e., ordered pairs of radionuclides and file names) may be given in the file $BIODEF.DAT
found in the biokinetic folder. If no directions are given in $BIODEF.DAT, then DCAL assumes that the
demarcation time between short-lived and long-lived is 15 d and, on the basis of the file names, decides which
biokinetic file to assign to a given radionuclide. If no files with root names ending in "_SUR" and "_VOL" are
found in the biokinetic folder, then the default biokinetic file [radioelement] .DEF is assigned.
In some cases, the fi value for material moving from the respiratory tract to the GI tract is assumed to depend on
the form of the radionuclide inhaled. The respiratory tract model of ICRP Publication 66(1994a) expresses this
in terms of an absorption type (Type F, M, or S). If the f value assigned to a specific form Q of an inhaled
radioelement X or XX is different from the f) value for the ingestion case, the form-specific f) value must be
defined in a file named X$Q.GF1 or XX$Q.GF1. That is, the root name consists of the abbreviation of the
radioelement, a dollar sign, and the form Q of the inhaled radionuclide, where Q is one of the letters F, M, or S.
If separate systemic biokinetic files are used for different chain members (i.e., if the option of independent
kinetics, i.e., of separate, pre-defined biokinetic files for separate chain members is selected), the systemic
biokinetic file for a decay chain member other than the parent must be of the form Y-X, Y-XX, YYX, or
YYXX, where Y or YY is the abbreviation of the decay chain member and X or XX is the abbreviation of the
parent. For example, a systemic biokinetic file for 222Rn to be used in a calculation for intake of 226Ra must
have the name RNRA.DEF. If the abbreviation of the decay chain member consists of only one letter, a hyphen
must be used in the second position because DCAL expects the first two positions to represent a decay chain
member other than the parent and the following position(s) to represent the parent.
3.7 DCAL'S INI FILE SYSTEM
DCAL's computational modules use INI files to specify the location of the permanent data files needed during
their execution. The default INI files are contained in the \DCAL\INI folder and should not require any editing
if the software was installed using the installation procedure. The INI file structure can be used to maintain the
integrity of the DCAL system while exploring alternative models and parameter values. Before attempting to
edit an installed data file, the user should consider using DCAL's INI file feature rather than compromising a
permanent data file. Before detailing this feature, it is necessary to understand the structure of the INI files.
The INI file structure was developed to provide the computational modules with access to a common set of
permanent data files and to ensure that the access was not limited by the coding. For illustrative purpose,
Fig. 3.3 list SEECAL's INI file.
17
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'RegMas s.aO 0' ,
.\dat\saf\RegMass.
aOO ' ,
0
'RegMass.aO1' ,
. \dat\saf\RegMass.
aO 1' ,
0
'RegMass.a05' ,
. \dat\saf\RegMass.
a05 ' ,
0
'RegMass.alO' ,
.\dat\saf\RegMass.
alO ' ,
0
'RegMas s.al5' ,
.\dat\saf\RegMass.
al5 ' ,
0
'RegMass.am' ,
.\dat\saf\RegMass.
am ' ,
0
'RegMass.af' ,
.\dat\saf\RegMass.
af ' ,
0
'PSAFTX66.aOO' ,
.\dat\saf\PSAFTX66
. aOO ' ,
126
'PSAFTX66.aOl' ,
.\dat\saf\PSAFTX66
.aOl' ,
126
'PSAFTX66.a05' ,
.\dat\saf\PSAFTX66
.a05 ' ,
126
'PSAFTX66.alO' ,
.\dat\saf\PSAFTX66
.alO ' ,
126
'PSAFTX66.al5 ' ,
.\dat\saf\PSAFTX66
.al5 ' ,
126
'PSAFTX66.am' ,
.\dat\saf\PSAFTX66
. am ' ,
126
'PSAFTX66.af' ,
.\dat\saf\PSAFTX66
. af ' ,
126
'ElAlphAF.aOO',
.\dat\saf\ElAlphAF
. aOO ' ,
0
'ElAlphAF.aOl',
.\dat\saf\ElAlphAF
.aOl' ,
0
'ElAlphAF.a05' ,
.\dat\saf\ElAlphAF
.a05 ' ,
0
'ElAlphAF.alO' ,
.\dat\saf\ElAlphAF
.alO ' ,
0
'ElAlphAF.al5' ,
.\dat\saf\ElAlphAF
.al5 ' ,
0
'ElAlphAF.am' ,
.\dat\saf\ELALphAF
. am' ,
0
'ElAlphAF.af' ,
.\dat\saf\ElAlphAF
. af' ,
0
' StdNames . t::t' ,
.\dat\mis\StdNames
. t::t' ,
0
'AF Alpha.lng' ,
.\dat\saf\AF Alpha
•lng',
0
'AF Elec.lng' ,
.\dat\saf\AF Elec.
lng' ,
0
' inde:-:. dat' ,
.\dat\nuc\icrp3::. nd::' ,
160
'radition.dat' ,
.\dat\nuc\icrp3::. rad ' ,
25
'beta.dat' ,
.\dat\nuc\icrp3::. bet' ,
9
'gamdos' ,
'linear'
f
0
Fig. 3.3 Listing of SEECAL.INI file.
Each line of an INI file has three comma-delimited fields. The first field is the name for the file as used in the
module's coding; thus, this field must not be changed. The second field is the relative path and name ofthe file
as existing in the indicated folder. The third field, if nonzero, is the record length of the file if it is a direct
access file. For example, this entry is the value of the variable RECL in FORTRAN open statements for a direct
access file. The numerical value depends on the compiler; hence, it was useful in the development of the
software to assign these values via the INI file rather than hard code it in the module. DCAL users should edit
only the second field. If necessary, the second field could be edited to include the drive designation. The
following example associates the decay data files in the folder NUC of drive F with the corresponding file name
in the module.
'index.dat' , :\nuc\icrp38.ndx' , 160
'radition.dat', :\nuc\icrp38.rad' , 25
'beta.dat' , :\nuc\icrp38.bet' , 9
All of DCAL" s computational modules check whether a copy of their INI file exists in the current work folder.
If the file is present, the module will use that file rather than the default INI file in the INI folder. This feature
makes it possible to evaluate changes to many standard parameters in the calculations without corrupting the
permanent data file. For example, to calculate SEE values using a special set of alpha absorbed fractions for the
respiratory tissues, the following steps should be followed:
1. Create a work folder for the investigation using from DCAL's Main Menu.
2. Copy the default SEECAL.INI from \DCAL\INI folder to the work folder.
3. Copy AF_Alpha.lng file from \DCAL\DAT\MIS to the work folder and rename it AF_Test.lng.
4. Edit the AF_Text.lng file as necessary.
5. Edit the SEECAL.INI file in the work folder to include the line
18
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,AF_Alpha. lng' , 'AFJTest.lng' , 0
It is not necessary to give the full path for AF_Test.LNG because it is in the work folder. This procedure can be
quite helpful in maintaining the integrity of system while using the system to carry out special investigations. It
is not necessary to use this approach when examining special biokinetic models, as such files can be placed in a
user-defined biokinetic folder.
19
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4.0 DCAL'S MAIN MENU
This section describes DCAL's main menu, which serves as the starting point for all calculations within the
system. The menu also provides access to a number of utilities and to parameter values that may aid the user s
efforts to validate a calculation.
4.1 INTERACTIVE MODE
DCAL's Main Menu can be invoked by either clicking on the DCAL shortcut on the desktop or from
Windows Explorer by clicking on DCAL2005.EXE in the DCAL folder. Fig 4.1 shows the DCAL Main
menu as it appears as a console application.
DCAL Main Menu Ver 8.3 June 26,2006
Uer. 8.3
U.S. Environmental Protection Agency
Dose and Risk Calculation System
" " 6-26-06
ctiuity as f»»»»»»»>
Uiew Work Files — 1ST
Plot Selected Data - LOTEM
Tabulate Dose Coeff— H AE
Nuclide Emissions — RA SUM
Decay Chain Details— hain
Batch Calculations - D ATCH
Systen Help — ELP
Compute activity us. time in compartments; to obtain U_50 .
=Help =Active Case =..\bioNfl3 =..NwrkSfgr!3 =About
Fig. 4.1. DCAL's main menu.
The DCAL2005 module obtains information on the user's past usage of the DCAL System from the file
DCALMENU.INI in the INI folder. Hie content of the INI file, as installed, is:
Default Directory
\bio\i68
\wrk\work
The second and third lines of the file identify the last used biokinetic and work folders, respectively, and are
used to initialize the next session. Only the path beyond \DCAL\DAT is included with the folder name. As
seen in Fig. 4.1, these assignments appear at the bottom of the menu screen and are labeled by the function
keys and , respectively. It is assumed that folders below \bio\ and \wrk\ are alternative biokinetic
and work folders, respectively. DCAL2005 constructs a list of such folders to appear in a menu that is
invoked by pressing either or . From the menu an alternative folder can be selected or a new folder
created. The name of the new folder is limited to no more than eight characters. If the user creates a new
folder, it will become the active folder.
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DCAL is limited to 15 biokinetic and 15 work folders and includes no provisions for deletion or removal of
folders from the system. However, a folder can be rendered inactive, that is not recognized by
DCAL2005 .EXE, by padding the folder name such that its length is greater than 8 characters. If a folder is the
default (active) folder do not attempt to delete it or alter its name.
DCAL's main menu is organized in two parts. The upper entries of the menu invoke the computational
modules for calculation of dose and risk coefficients. The lower entries invoke various utilities and the batch
computational facility. The calculations must be carried out in a particular order. As the calculations precede
the DCAL menu will appear with the selection bar generally positioned at the next step in the calculations. For
example, calculations of the dose coefficient for the inhalation of 60Co in the workplace would proceed by first
invoking ACTACAL, then SEECAL, then EPACAL. The results of the calculation could be summarized by
invoking the HTAB utility and all files for this cased can be viewed by selecting LIST.
Note that as the menu select bar is moved by the up/down arrow keys, a one-line description of the menu item
appears on the screen. More detailed information for each menu item is available by pressing . Table 4.1
lists each menu item with a brief discussion of its purpose. DCAL uses the up/down arrow key to move within
menus. In the current version of DCALMENU the mouse is not used for such purposes and is not only
operable within DCAL's utilities PLOTEM, LIST(PBVIEW), RADSUM, and CHAIN. See Chapter 12 for
further information on DCAL's utility modules.
The line at the bottom of the main menu notes the assignment of the function keys, through . The
default display covers through and the assignments for through can be seen by
pressing the space bar. Table 4.2 explains the purpose of each of the function keys.
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Table 4.1. Purposes of modules and utilities available in DCAL main menu.
Module or
Utility
Purpose
This is the starting point for all calculations involving the intake of a
radionuclide. The module calculates activity as a function of time in
body compartments following unit intake at an indicated age.
This computes the dose rates in the target tissues per unit activity
residing in the source organs (SEE values) for the radionuclides
identified by ACTACAL, for the commitment period. Calculations are
for reference individuals of ages 0, 1-, 5-, 10-, 15-y, and adult, or
ages selected by the user from this set.
This calculates the dose rates in the target organs based on the time-
dependent activity in source organs generated by ACTACAL and the
SEE values for the source-target pairs generated by SEECAL. The
committed dose is computed as the time integral of the dose rate.
This computes the health risk based on the absorbed dose rate files
for the reference individuals, assuming an age-dependent intake
function. External exposures are age-invariant.
This computes the external dose conversion coefficient for a user-
provided radionuclide and environmental medium.
This utility is used to view output files in the indicated work folder.
This provides a graphical display of the activity or dose rate data.
The activity of each member of a decay chain is displayed.
This generates a table of committed doses for the target organs for
each reference individual considered in the calculation.
1.ACTACAL
2. SEECAL
3. EPACAL
4. RISKCAL
5. EXTDOSE
6. LIST
7. PLOTEM
8. HTAB
9. RADSUM
10 CHAIN
11. DBATCH
12. HELP
This utility summarizes the radiation emissions, specific activity, and
gamma constant of a user-selected radionuclide. Radioactive
progeny are identified with applicable branching fractions.
This utility displays the decay chain with the members' branching
fractions and energies of emissions. Cumulative energies of alpha,
electron, and photon emissions over a 100-year period are shown as
a guide to truncation of the chain in dosimetric calculations if desired.
This is DCAL's batch computation facility.
This menu item provides the user with access to various data files
and help files regarding the DCAL system.
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Table 4.2. Purposes of the function keys of the DCAL main menu.
Key Function
This key provides a brief explanation of the highlighted menu item.
This key shows the current (active) interactive case. Familiarity with the file-
naming convention enables identification of the radionuclide, intake mode, dose
type, and age. If ACTACAL is run with the desired dose type (absorbed or
equivalent) not properly identified, the key combination Shift+F1 will toggle
between the two dose types.
This key enables the selection (or creation) of a biokinetic the folder containing
the systemic biokinetic models.
This key enables the selection (or creation) of a work folder for the output files
generated by DCAL.
This key provides the usual software "about" listing the individuals involved in
the development of DCAL and its sponsor.
This key invokes the ACTINT32.EXE utility to calculate the number of nuclear
transformations of each member of the decay chain in the source organs during
the 50-year period following a unit intake of the parent radionuclide.
This key invokes the DRTINT32.EXE utility to integrate of the dose rate in each
target organ over the time periods defined in the global DRTINT.INI file in the INI
folder or the local DRTINT.INI in the work folder.
This key invokes the BIOTAB32.EXE utility to tabulate the 24 hr urinary and
fecal excretion and the retained activity in the body as a function of time.
This key invokes the EXPORTM utility for the export of a DCAL output file
(activity or dose) in a format suitable for import into a spread sheet program,
e.g., Excel.
This key invokes the DCALSYS utility to generate a table of DCAL's permanent
data files currently on the computer.
This key displays the pdf of this document. This function works only if files with
the extension pdf are registered to be opened in Windows by a suitable reader.
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5.0 INTERACTIVE IMPLEMENTATION OF DCAL
This section describes how to run DCAL using an existing library of biokinetic files, in the interactive mode.
Later sections describe how to run DCAL in the batch mode and how to expand the library of systemic
biokinetic models and/; values for elements by adding user-supplied files.
5.1 STEPS IN AN INTERACTIVE RUN OF DCAL
To initiate an interactive session, follow the three steps described below. After the third step has been
completed, DCAL will invoke the ACTACAL module, which issues a series of prompts. At each prompt, a
selection is made by pressing for the default selection or typing in the selection (an identifying letter or
number) and pressing . The prompts will carry you through the end of the activity calculations, after
which remaining steps in the dosimetric calculations are invoked from the DCAL main menu.
Step 1: To begin the session, click on the DCAL shortcut on the desktop.
The DCAL main menu will appear (Fig. 4.1). Menu item are selected by using the arrow keys to position the
menu bar on the item and then pressing or, when available, press the "hot key" indicated by a
highlighted letter in the menu item.
Step 2: Determine that the folder containing the desired systemic biokinetic model and f_ value is active.
Methods for defining an alternate biokinetic model or fL value are described later.
In the bottom line of the DCAL main menu, the name of the active biokinetic folder appears after "=".
There are two main biokinetic folders:
..\BIO\l68,
..\BIO\F13.
The folder 168 contains systemic biokinetic model files and f files based on models and assumptions given in
ICRP Publication 68 (1994b) on occupational exposure. The folder F13 contains systemic biokinetic model
files and f files used to generate the risk coefficients in Federal Guidance Report 13 (EPA 1999). In addition,
there is an initially empty biokinetic folder, \DCAL\DAT\BIO\USR, intended to contain user-constructed
systemic biokinetic and fi files. To change the currently active biokinetic folder (i.e., to select the desired
systemic biokinetic model and f value), press and select the proper folder from the overlying menu that
appears. Once the item is highlighted it is selected by pressing the key.
The bottom line of the DCAL main menu also indicates the work folder that will receive DCAL output, after
"=". To change the work folder, press and select from the choices given in the overlying menu that
appears. Three work folders are initially created as an aid in organizing output if several cases are to be
considered:
..\WRK\WORK
. . \WRK\WORK2
..\WRK\FGR13.
After selection of the desired folder in the manner discussed above, the DCAL Main Menu becomes active.
Step 3: Select "Activity as f(t)" (activity as a function of time) on the DCAL main menu and press .
This selection initiates an interactive session by invoking the module ACTACAL, which calculates the activity
as a function of time in the compartments specified in the biokinetic data files, including the compartments of
the gastrointestinal tract and, for inhalation intakes, the compartments of the respiratory tract. ACTACAL
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performs the following functions: (1) it prompts you to describe the route of intake, the parent radionuclide,
exposure mode, and, for the inhalation case, size and absorption type or solubility classification of inhaled
particles; (2) it uses the biokinetic files to define the compartment model, establish the transfer rates between
compartments, and define the source organs to be used in dose calculations; and (3) it calculates the activity of
the parent and its radioactive progeny in each source organ as a function of time.
Where feasible, the prompts issued by ACTACAL provide various options given in parentheses and a default
response given in square brackets. The default can be accepted by pressing . A response other than the
default must be typed and followed by .
The first piece of information to be supplied is the parent radionuclide taken into the body. The request for a
radionuclide follows a set of screen messages as shown below.
ACTACAL: Activity calculation
Ver. 6.1 (Dec 22, 2003)
Authors: K.F. Eckerman & R.W. Leggett
Oak Ridge National Laboratory
Oak Ridge, TN 37831-6383
Output Folder: ..\wrk\work2
Biokinetic Folder: ..\bio\i68
Input parent nuclide (e.g., Sr-90) ->
As described earlier, you may enter any of the 825 radionuclides considered in the preparation of ICRP
Publication 30, plus 13 other radionuclides considered more recently considered by MIRD. You may also enter
the symbol for a stable element (e.g., K or Ca) with no atomic weight. In this case, ACTACAL solves the
biokinetic model for the element assuming no radioactive decay. ACTACAL will check that the entry is a valid
radionuclide, i.e., that the nuclear decay data for the nuclide are contained in the files of the folder \DAT\NUC.
You are then asked if you want to perform calculations for a set of reference individuals specified in the file
INTAKEXP.AGE.
I so lho ddiiiill age file: IM AKIAKAdK: (|y|/n)? y
The default ages at intake are defined in the data file INTAKEXP.AGE contained in the folder
\DCAL\DAT\MIS. The file contains the six ages at intake considered in ICRP's series of documents on doses to
the public from intake of radionuclides, i.e., infant (100 d), 1 y, 5 y, 10 y, 15 y, and adult. The adult is 20 y
(7300 d) in most cases, but this depends on the biokinetic model. In biokinetic models in folder
\DCAL\DAT\BIO\F13 that involve transfer rates based on bone turnover rates (models for Ca, Sr, Ba, Pb, Ra,
Ac, Th, Pa, U, Np, Pu, Am, and Cm), mature adulthood is assumed to begin at age 25 y (9125d) because of
substantial changes with age in bone turnover rates between ages 20 and 25 y.
If you select the default answer, [y] (yes), then separate calculations are performed for intake at each of the
acute ages defined in the INTAKEXP.AGE file. If the answer to the above prompt is no, you are then prompted
to specify the number of ages to be considered in the DCAL run. DCAL's modules can address 10 ages.
As indicated by the subsequent prompts for selected ages, the ages should be entered in days rather than years.
You will be prompted for the next age until the indicated number of ages has been entered.
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Input number of ages, < 11 ->
Enter age at exposure (integer format)
1 - age (d) ->
To avoid duplicate calculations, you should be familiar with the extent of age dependence, if any, considered in
the biokinetic models and in SEE values used in the calculation. For example, suppose the calculation is for
ingestion of 238U and two ages are selected, 7300 d and 9125 d (20 y and 25 y, respectively). If the systemic
biokinetic model selected is from the folder \BIO\I68, then the output will be identical for the two ages because
the model for U in that folder includes parameter values only for the adult. If the systemic biokinetic model
selected is from the folder \BIO\F 13, then the output will be different for ages 20 y and 25 y because in this case
the biokinetic parameter values are assumed to vary linearly with age until the adult age (in this case, 25 y) is
reached. That is, the values for the 20 y old will be based on an interpolation of the biokinetic parameters
assigned to the 15-y old (5475 d) and the 25-y old (9125 d).
Note that the age at intake is not restricted to the ages at which the biokinetic model is defined or
to ages for which absorbed fraction data ha\e been tabulated. IH'AI. demos data for ages other
than those specified in the model by interpolation. Thus users can edit the lYIAklAP.ACE file
in l)CAI.\l)AT\MIS as needed.
The next inquiry concerns the dose quantity of interest.
Compute (a)bsorbed or (c)qimalenl dose (a/|c|)?
Equivalent doses are based on the radiation weighting factors currently recommended by the ICRP (1 for
gamma, beta, or electron radiation, 20 for alpha radiation, and 5 for spontaneous fission neutrons). If risk
coefficients are to be calculated, then absorbed dose quantity must be selected.
ACTACAL normally tabulates the activity as a function of time in source regions of the body. Depending on
the biokinetic model, a source region may include multiple compartments. The next inquiry provides an option
to generate a file detailing the activity in the various compartments in the biokinetic models.
Compute compartment source region aclmly: (|n|/v)?
If the answer to this prompt is yes, ACTACAL will generate an additional file with extension CPT that lists the
inventories of individual compartments in the biokinetic model, rather than simply the inventories of source
regions used in subsequent dosimetric or risk calculations. This option is included to allow a detailed evaluation
of ACTACAL's solution of the biokinetic model. For example, this option might be used to determine the
cumulative urinary or fecal excretion predicted by the biokinetic model or to investigate the source of
unexpected predictions of the biokinetic model.
The mode of intake is addressed in the next prompt.
Intake \ia: in( j)cclion. in(h)alalion. or in(g)cslion: ( j/h/|g|)?
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Injection refers to instantaneous entry of 1 Bq of the radionuclide into blood. Inhalation refers to instantaneous
inhalation of 1 Bq of the radionuclide; only a portion of the inhaled activity will be deposited in the respiratory
tract, with the shortfall being exhaled. Ingestion refers to instantaneous deposition of 1 Bq of the radionuclide
in the stomach. If the selected intake mode is either injection or ingestion, no further information on the intake
scenario is required, although prompts regarding other information will follow.
For inhalation intakes you are requested to select an absorption type for the aerosol as defined in the respiratory
tract model (ICRP Publication 66, 1994a).
I.un» iihsorplion typo: (l'):ist, (in(odontic, or (s)low (|l'|/in/s)?
After selecting an absorption type, you will also be asked to specify whether this is an environmental or
occupational exposure. DCAL's default aerosol size is an activity median aerodynamic diameter (AMAD) of 1
(.im for environmental exposures and an AMAD of 5 (im for consideration of occupational exposures in the
absence of specific information about the physical characteristics of the aerosol.
Input AMAI); dol'milt is I urn ->
After the intake mode has been selected and, if applicable, any of the above follow-up questions concerning
inhalation intakes have been answered, you are given the opportunity to enter additional documentation of the
cases which will appear in the log file. After you enter the first line of text by pressing , you are
prompted for line 2 of text, and so forth, until you have entered the maximum number of lines or have pressed
after a blank line.
Input text inforniiition. M;i\.() linos, hhink to lorniiiiiito ro:ul.
I.
As discussed in Chapter 3, DCAL output files have standard names, all beginning with the name of the
radionuclide. The LOG file generated for the ingestion of 90Sr by the adult would be SR-90AG_.LOG, where A
denoted adult, G denotes ingestion, and the underscore completes the eight-character root name for the file. If
the standard output file names coincide with existing files in the active output folder, you will be warned and
will be given the chance to change a character in the file names. For example,
I'ilo Sr')OA«_ oxisls!
|o|\or\\rilo or |r|on;imo I'ilo (|«»|/r)? o
If your response is to rename the output files, you are asked for a new last character.
Now hist chiinu-tor (o.*».. /) ->
Next, you are shown two tables of information, based on data contained in the nuclear decay data index file in
the folder \DCAL\DAT\NUC, concerning the radionuclide and any radioactive progeny. If both tables cannot
be shown on a single screen, the first table is displayed and the system pauses until you press any key. The first
table includes the radiological half-lives and branching fractions for the members of the chain. The second table
includes the number of transformations over a 100-year period and the cumulative energies, separated by type
27
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of radiation, over the same period. For example, the two tables for 90Sr are as follows:
Sr-90 Decay Chain: Half-lives and Branching Fractions
Nuclide Halflife fl Nuclide f2 Nuclide f3 Nuclide
1 Sr-90 29.12y 1.0+00-> 2 Y-90
2 Y-90 64.Oh
Sr-90: Activity, Transformations, & Cumulative Energies (MeV) at lOOy
Nuclide Tl/2 A(t)/Ao intA/Ao(d) Ealpha Ebeta Egamma
1 Sr-90 29.12y 9.25216D-02 1.39249D+04 0.00E+00 2.73E+03 0.00E+00
2 Y-90 64.Oh 9.25448D-02 1.39246D+04 0.00E+00 1.57E+04 0.00E+00
The numerical values tabulated in the last three columns of the second table represent the cumulative energies
emitted by alpha, beta (including discrete electrons), and photons (gamma and x-rays) for nuclear
transformations occurring over 100 years in a sample consisting initially of 1 Bq of the parent. The columns in
the second table labeled "A(t)/Ao" and "intA/Ao(d)" represent, respectively, the fractional activity present at
100 y and the fractional integrated activity (d) at 100 y.
These tables serve two main purposes. First, they remind you of the chain members whose biokinetics must be
addressed in some manner, either explicitly through separate biokinetic files or implicitly through some blanket
assumption (e.g., no translocation of decay products, or decay products inherit biokinetics of parent). Second,
by showing cumulative energies associated with different segments of the chain, they help you determine
whether the decay chain may be truncated without substantially affecting dose estimates. Although ACTACAL
makes such a decision based on a virtual lack of increase in cumulative energy beyond some chain member, you
may select a higher or lower cutoff point in the chain if you decide that is appropriate for the problem being
addressed.
If radioactive progeny exist, you will be given different options concerning the biokinetics of chain members.
Isokinetics of l)ec:i> C'hiiin Members
Options to iiddress biokinetics ol'deciiy cliiiin members:
1. Independent kinetics; user-predefined files.
2. Shiired kinetics; ICKP-30 ;ippro:ich.
Item 1 is a valid option only if the necessary biokinetic files for all members of the decay chain exist within the
active biokinetic folder selected at the beginning of the interactive session. ACTACAL searches the biokinetic
folder for pre-defined files for all chain members before giving the above prompt. If such files are not available
for all chain members, Option 1 is replaced with "Independent kinetics N/A; predefined files not found", and
only Items 2 and 3 are shown in the prompt.
The treatment of radioactive progeny in biokinetic and dosimetric calculations is addressed in detail in Section
9. Briefly, a standard approach has been to use the assumption of shared kinetics, i.e., to assume that the
biokinetics of a decay chain member is the same as that of the radionuclide taken into the body (called the
parent radionuclide). This approach was used in ICRP Publication 30, with the exceptions that noble gases
produced in vivo and iodine produced in vivo from decay of tellurium isotopes were assigned kinetics
independent of the parent. For most radionuclides, this assumption has been carried over to later ICRP
publications and to Federal Guidance Report 13 (EPA 1999). For isotopes of a few elements, including lead,
radium, uranium, and thorium, it is assumed in recent ICRP publications and in Federal Guidance Report 13
that decay chain members produced in vivo have "independent kinetics". This means that a radionuclide born in
soft tissues or on bone surfaces redistributes in a manner consistent with its own characteristic biokinetic model,
28
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and, in effect, the rate of translocation of a radionuclide born in bone volume is determined by the rate of
restructuring of bone.
If you select item 3 from the options concerning decay chain members, you will be further prompted, as
indicated below.
Member-by-member default options:
;i. No hiolo<>ic;il lr;insloc;ilion.
h. Prompt remo\;il from the body,
c. Assign kinetics of first member.
Respond to memher-hv-memher query.
|\:ime of clinin memher|: - Options: si. h, c - (:i/h/|c|)?
Item a assumes the chain member remains at the site of production. Item b is implemented by assuming a
transfer rate of 1000 d"1 from the site of production to "Excreta". Item c differs from the assumptions of ICRP
Publication 30 only in that noble gases and isotopes of iodine are not treated as exceptional cases.
After selections have been made concerning the systemic biokinetics of chain members, ACTACAL checks the
biokinetic files for consistency regarding paths of movement of systemic activity. Two types of checks are
made. First, if potential absorption or reabsorption of any chain member from the GI tract to blood is implied
by the selected intake mode or the systemic biokinetic model, then ACTACAL checks whether the appropriate
ft file exists in the active systemic biokinetic folder. Second, if the option of pre-defined kinetic models for
different chain members has been selected, then ACTACAL checks for consistency in the systemic biokinetic
files for different chain members. In particular, ACTACAL checks whether the file for each chain member
describes outflow of activity from all compartments that receive any higher chain member.
If a required f) file is missing from the active systemic biokinetic folder, you will receive a prompt, as illustrated
here for 239Pu.
The I I file for l'u-231) does not exist!
Do you \\:inI to cresile the file now (\Y|n|)?
If you choose the default, that is, not to create the f file, ACTACAL will abort. If you choose to create an f)
file, then ACTACAL provides a series of prompts, as illustrated here for 239Pu.
C're:iliii» I I file for l'u-231)
Input number of :i»es ->
If a single f) value is to be applied to all ages, enter "1". If age-specific f) values are to be considered, values
linearly interpolated by age will be applied by ACTACAL to intermediate ages. After you have entered the
number of ages, you are asked to provide a descriptive title line for the f) file being created.
Input title line: < 73 ch;ir;iclers ->
Next, ACTACAL requests the age and f) value for each age group.
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Knlor :i»e (integer) »S I I (restI) sep:ir:iled In :t spnee.
I ->
After the age and f) value for that age have been entered, values for the next age are requested.
If there is a missing compartment in the systemic biokinetic file for some chain member, a prompt will appear
(radionuclide and compartment name are illustrative).
No remo\ :il of l*«-210 from comp;irlmcnl kidneys! is profiled.
Options included:
:i. No biolo«.iic:il i ciiioxiil.
h. Prompt transfer to hlood.
c. Abort iind correct files.
I se: :i. No remold. h. Prompt rcino\:il, c. Abort (:i/|b|/c)?
After a selection is made, ACTACAL will continue to give similar prompts, one by one, until all missing
transfers have been assigned values. The supplied transfers are not entered into the permanent DEF files but are
used only in the present application. Therefore, it is usually best to abort and insert the missing transfers in the
DEF files for future use rather than attempting to patch the problem interactively. However, it is useful to let
ACTACAL identify all missing transfers before aborting. This is accomplished by making arbitrary selections
at each prompt so that the next prompt will appear. If you are applying the library of models of ICRP
Publication 68 (1994b) (folder \DCAL\DAT\BIO\I68) or Federal Guidance Report 13 (folder
\DCAL\DAT\BI0\F13) and are following the assumptions concerning chains of radionuclides described in
those documents, then the problem of missing transfers should not arise.
If no inconsistencies of the types described above are found in the biokinetic files, then ACTACAL begins
calculations of activity as a function of time after intake. As calculations start, ACTACAL writes brief credits
to the screen, such as the version number of the code and the names of the authors. The screen will show that
computations of time-dependent activity have begun and will continually show the progress made by giving the
last time (i.e., days after intake) for which activities were output to the activities file (extension ACT). For
example, when day 1000 has been reached in calculations for ingestion of 90Sr by the adult (age 9125 d), the
screen will show the following:
MAJOR l>KO(iKAM I.OOP: compulsions lor :ij>e # I («>l25d)
C'ompuliitions stiirted; time post inliikc = I(MM).(M) d.
When calculations of activity are complete, a message similar to the following will appear on the screen
(numbers and file name are illustrative):
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C 'onipiiliilions stiirlcil; lime post inlsikc = 28000.00 d.
Atliiincd :i«o > 100 y: compnt:itions hiilled.
System of 34 simiilliincoiis dilTcrcnlinl equations solxcd in 2.5 s.
Acli\ilics written lo file Sr-'JOA" .AC "I".
SKIX'AI. request file written: Sr-'JOAji.rcq
I'rogriim AC I AC AI. ended norninllv.
The message concerning the "SEECAL request file" indicates that ACTACAL has created a file, to be read by
the SEECAL module, listing the source and target regions that should be considered in the SEE calculations.
The message that the program has ended normally is followed by a DCAL prompt:
Press :my key lo continue ...
When a key is pressed, the DCAL main menu will appear and the second menu item (SEECAL) will be
highlighted:
SKK Ciilciihilions - SKKCAI.
If dose calculations are not desired, press . You will be returned to the DOS prompt in the work folder.
The generated activity file, whose name begins with the radionuclide and which has the extension ACT, can be
found in that folder. If dose calculations are desired, press to start SEE calculations by the module
SEECAL. From this point forward you are not required to provide any additional information regarding dose or
risk calculations, but you will be returned to the DCAL main menu at some stages in the calculations and given
options concerning the type of further calculations to be performed.
As SEE calculations start, SEECAL writes brief credits to the screen, such as the version of the code and the
names of the authors. Next, information on the radiation types associated with the parent radionuclide and decay
chain members appears on the screen. The information is updated as the calculations progress. The case of
ingestion of 90Sr by the adult is used here to illustrate the messages written to the screen by SEECAL.
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MAJOR PROGRAM LOOP: working on age # I (iulull male)...
Rending photon SAI's lor age = :ulult male ...
Rending electron nlplin Al s lor nge = itclull male ...
(nlculnting SKKs lor nuclide = Sr-'>0 ...
I'or hetn +/- particles (11= I)
Calculating SKKs I'or nuclide = Y-')0 ...
I'or photons < lOkcY (11= 12)
I'or photons >= It) keY (11= S)
I'or helsi +/- particles (11= 2)
for nionoen. electrons (11= 25)
The following SKK files ha\e heen written:
sr^Hit.si:!-: y<>oiu.si-:i-:
If the decay mode of one of these radionuclides includes spontaneous fission, you will be warned if the version
of SEECAL does not handle radiations from spontaneous fissions and that such radiations will be ignored.
Information concerning the frequency and energy of different spontaneous fission radiation types is also written
to the screen.
The message that the program has ended normally is followed by a DCAL prompt:
Press sinv key to continue ...
When a key is pressed, the DCAL main menu will appear with the third item on the menu (EPACAL)
highlighted:
Compute Dose - KI'ACAI.
Press to begin dose calculations. The principal task of the EPACAL module is to combine the time-
and age-specific activities calculated by ACTACAL with the age-specific SEE values calculated by SEECAL to
calculate dose rates to target organs. EPACAL output is in the form of absorbed dose rate or equivalent dose
rate calculations, depending on whether you selected "absorbed dose" or "equivalent dose", respectively, early
in the interactive session. If "equivalent dose" was selected, the SEEs computed in apreceding step will include
radiation weighting factors for different radiation types. EPACAL output can be found in the active output
folder. The name of the output file will begin with the parent radionuclide and will have extension DRT if
absorbed dose was selected and HRT if equivalent dose was selected.
As EPACAL calculations start, EPACAL writes brief credits to the screen, such as the name and version of the
code and the authors. Next, information on the radiation types associated with the parent radionuclide and
decay chain members appears on the screen and is updated as progress is made by EPACAL. Also, some
warnings may be given to alert the reader to certain conventions or assumptions used in the calculation. In the
following, the case of ingestion of 90Sr by the adult is used to illustrate the messages written to the screen by
Menders in sill SKK files m:ilchcd OK.
Source organ iiiinies in aclmly SKK files mulched OK
Youngest age for SKK \ sillies to he resul is: 7300 days (sidult m:ile)
MAJOR PROdRAM I.OOP: working 011 aclmly file # I (Sr-«>0Ag .sict)...
Rending SKK file for i\uc = I (Sr-4)0)...
Rending aclmly file for i\uc = I ...
Calculating dose rsites for i\uc = I ...
-------
EPACAL. It is assumed here that you have elected to compute equivalent dose rather than absorbed dose.
The above three lines are repeated for 90Y, iNuc=2, and concluded with
Writing dose rsites to dose rsile file # I (SR-'WAC.I IRT)...
The following dose rsile files h:i\e been written:
SR-<)0.\(; .MR I
Program KI'ACAI. ended norniidly.
The message that the program has ended normally is followed by a DCAL prompt:
Press nny key to continue ...
W hen a ke\ is pressed, llie DC Al. main mam will appear The I'ouilh ilem on llie menu will Iv hiijhliijhlei:
Com pule Risk - RISKC Al.
If the absorbed dose option was selected earlier, a table of risk estimates may be calculated (by the RISKCAL
module) by pressing . The screen will show brief credits for RISKCAL, followed by the message:
Input diitii files were successfully rend.
As RISKCAL goes through organ-by-organ calculations of cancer risk from the specified intake, the screen will
show the current stage of the calculation. For example:
Computing risks for ciincer: esophiigus
After all risk calculations are complete, you will see a message similar to the following:
Tile: SR-'MAC .RliS written successfully.
RISKCAL termiiiiited norniidly.
In addition to the indicated file with extension RBS, a file with the same stem and extension RSK has been
written to the active work folder. The file with extension RBS contains age- and gender-specific and total
estimates of radiogenic mortality and morbidity by cancer site. The file with extension RSK records the risk of
cancer.
The messages indicating completion of risk calculations are followed by a DCAL Prompt:
Press key to continue...
When a key is pressed, the DCAL menu will appear. The first item under "UTILITIES" will be highlighted:
The utility LIST is included as a convenient way of examining DCAL output files written into the work folder.
DCAL Work I iles - LIST
TTD
-------
If you press , a list of files in the active work folder will be shown. The mouse or arrow key can be
used to move to the file of interest. Pressing will reveal the file contents. Arrow keys can then be used
to scroll or to move to the right to view any portion of the file. Pressing twice will return you to the
DCAL folder in the DOS path environment. See Section 12.1 for further options regarding the LIST utility.
If you selected the equivalent dose option earlier and want to calculate dose coefficients, move the menu bar to
the third entry in the utility section of the menu
hihnhite Dose C oelT- IITAIS
Then press to generate a concise table of "dose coefficients", similar in form to the tables provided in
the ICRP's series of documents on doses to the public from intake of radionuclides (ICRP 1989, 1993, 1995a,
1995b, 1996). The table can be found in the active output folder and will have a name beginning with the
parent radionuclide and with extension HEF. For each intake age considered, the table provides a list of
committed doses, or committed equivalent doses, to each organ given in the standard list of target organs. The
committed dose values are based on an integration period of 50 y for intake by adults and integration from time
of intake to age 70 y for intake by children. The table will also include an effective dose for each age group.
The effective dose takes into account that the relationship between equivalent dose and the probability of
radiogenic effects depends on the organ or tissue irradiated. The effective dose is a weighted sum of equivalent
doses to radiosensitive tissues, with the tissue weighting factor representing the relative contribution of that
tissue to the total detriment for the case of uniform irradiation of the whole body. Tissue weighting factors used
in DCAL are those recommended in ICRP Publication 60 (1991). If the "absorbed dose" option is selected and
the parent radionuclide or some chain member emits high-LET radiations, the calculated effective dose will not
be meaningful because the radiation weighting factors for high-LET radiations were not considered in the
calculation of SEE values.
If you select the HTAB utility, a message similar to the following appears on the screen. The case of ingestion
of 90Sr by the adult is used here for illustrative purposes (see listing in Fig 5.1).
Tiihiihite Agc-Dcpciulcnt Dose Coefficients
Working on file SR-'MAg.l IkT...
Working on file SR-')0 lig.MRT...
Working on file SR-')0 Cg.l IRT...
W orking on file SR-')0 Dg.llRT...
W orking on file SR-'X) Kg.llRT...
W orking on file SR-90 I"g .MR I ...
The file SR-'MAg.lIKI-" hits been written.
Press ;iii\ key to return to DCAL menn.
When a key is pressed, the DCAL main menu will appear. Again, the first item in the utility section of the
menu will be highlighted:
IK'AI. Work I iles - LIST
5.2 ACTACAL AND SEECAL INI FILES
34
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In addition to their normal role, the INI files for ACTACAL and SEECAL each direct an aspect of their
module's computations. The last entry of ACTACAL.INI is
'ThaifDays' , '1.0' ,0 Short Halflife
This line controls how ACTACAL handles short-lived radionuclides. For these radionuclides, no changes with
age occur in the biokinetic or in organ sizes, so that the time-dependent details of the dose calculation are of
little interest. ACTACAL acts on the above entry by scanning the decay chain to determine if the half-life of
any member exceeds 1.0 d. If no such members are found, then ACTACAL will calculate the number of
nuclear transformations (integral of the activity) in the source regions rather than activity as a function of time.
EPACAL, when seeing only one datum per source organ, assumes the entries are the number of nuclear
transformations. Similarly, RISKCAL assumes that the dose is delivered instantaneously as if it were external
irradiation.
The last entry in the SEECAL.INI file is
'gamdos', 'linear', 0 Interpolation scheme
This line defines the nature of the scheme by which the photons SAFs, as a function of energy, are interpolated
in the calculations. The SAF library includes photon SAFs for each source-target pair for 12 monoenergetic
photon sources. The above entry invokes linear interpolation in computing the contribution of the photon
emissions of the radionuclide to the SEE value for the source-target pair. Linear interpolation in energy has
historically been applied to the photon SAF data and continues to be used. SEECAL provides a log-log
interpolation scheme using spline routines. To use this scheme, the entry for the second file is "pchip loglog".
SEECAL will issue an error message if a proper interpolation scheme is not indicated in its INI file.
35
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DCAL Main Menu Ver 8.3 June 26,2006
Sr-90 Ingestion Committed Equivalent Dose Coefficients marked by ' *' are based on splitting of remainder weight.
Output file: Sr~90Ag_.hef
« HTAB32 Uer 6.0 CJuly 30, 2004> Run Jly 10, 2006, at 15:03 »
Sr-90flg_.hef - 7/10/2006 3:03 PM | 4/. | tl-n- PgDn PgUp | E:
3m 1 Year
0.6 0.4 0.4 0.4
1.18E-08 5.45E-09 2.85E-09 1.75E-09 1.13E-09 6.62E-10
1.57E-08 7.57E-09 4.97E-09 3.60E-09 2.66E-09 1.48E-09
2.27E-06 7.29E-07 6.34E-07 1.05E-06 1.81E-06 4.07E-07
1.18E-08 5.45E-09 2.85E-09 1.75E-09 1.13E-09 6.62E-10
1.18E-08 5.45E-09 2.85E-09 1.75E-09 1.13E-09 6.62E-10
1.48E-08 7.09E-09 3.64E-09 2.19E-09 1.43E-09 8.99E-10
1.48E-08 8.44E-09 4.34E-09 2.63E-09 1.62E-09 1.13E-09
6.01E-08 4.30E-08 2.15E-08 1.27E-08 7.23E-09 5.83E-09
1.89E-07 1.50E-07 7.52E-08 4.42E-08 2.52E-08 2.19E-08
1.18E-08 5.45E-09 2.85E-09 1.75E-09 1.13E-09 6.62E-10
1.18E-08 5.45E-09 2.85E-09 1.75E-09 1.13E-09 6.62E-10
1.18E-08 5.45E-09 2.85E-09 1.75E-09 1.13E-09 6.62E-10
1.18E-08 5.45E-09 2.85E-09 1.75E-09 1.13E-09 6.62E-10
1.18E-08 5.45E-09 2.85E-09 1.75E-09 1.13E-09 6.62E-10
1.18E-08 5.45E-09 2.85E-09 1.75E-09 1.13E-09 6.62E-10
1.18E-08 5.45E-09 2.85E-09 1.75E-09 1.13E-09 6.62E-10
1.51E-06 4.16E-07 2.72E-07 3.71E-07 4.82E-07 1.78E-07
1.18E-08 5.45E-09 2.85E-09 1.75E-09 1.13E-09 6.62E-10
1.18E-08 5.45E-09 2.85E-09 1.75E-09 1.13E-09 6.62E-10
1.18E-08 5.45E-09 2.85E-09 1.75E-09 1.13E-09 6.62E-10
1.18E-08 5.45E-09 2.85E-09 1.75E-09 1.13E-09 6.62E-10
1.18E-08 5.45E-09 2.85E-09 1.75E-09 1.13E-09 6.62E-10
1.18E-08 5.45E-09 2.85E-09 1.75E-09 1.13E-09 6.62E-10
1.18E-08 5.45E-09 2.85E-09 1.75E-09 1.13E-09 6.62E-10
1.18E-08 5.45E-09 2.85E-09 1.75E-09 1.13E-09 6.62E-10
1.18E-08 5.52E-09 2.88E-09 1.77E-09 1.14E-09 6.71E-10
2.27E-07 7.23E-08 4.67E-08 5.96E-08 7.86E-08 2.76E-08
5 Year
0.4
10 Year 15 Year
0.4
Exit
Fig. 5.1. Listing of HEF file of age-specific equivalent dose coefficients for ingestion of Sr-90.
5.3 INTERACTIVE HOUSEKEEPING PROCEDURE
During the course of an interactive session DCALs ACTACAL module creates several files specific to the
current case. This include a log file (*.LOG) containing information from all the computational modules, the
REQ file by which ACTACAL communicates with SEECAL, and SEECAL's SEE files for the case. These
files should be reviewed by the user; particularly when implementing new biokinetic data or when a
computational problem is indicated. All files specific to the current interactive case are available for viewing
using the LIST menu item. However upon the next issuance of ACTACAL the LOG, REQ, and SEE files of
the previous case are deleted. This procedure provides a bit of housekeeping to limit the accumulation of files.
An annotated set of files created in the interactive calculation of the 10 Ru inhalation dose coefficient for
workers can be found in Appendix A.
36
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6.0 DCAL's BATCH MODE FACILITY
This section discusses the batch mode of operation of DCAL. This mode of operation can be used to process a
user-defined set of nuclides for calculation of dose and risk.
Recall that in the interactive mode, the DCAL modules are driven by selections of operations from the DCAL
main menu. All input comprising a DCAL run is assembled by the module ACTACAL and then passed to
subsequent modules, either within specific input files accessed by the module or through a file named
SStemNam.Dir. Several intermediate files written during the course of DCAL's calculations are saved for the
purpose of quality assurance of DCAL output.
The batch mode of operation is provided for "production-type" calculations. In the batch mode, the sequence in
which the computational modules are invoked and their input data are defined in a user-supplied input file. The
input file also identifies the intermediate data files written during the course of DCAL's calculations that are to
be deleted after cycling through the sequence of computational modules. This "house-keeping" option is
provided because the total required storage space for these relatively large intermediate data files may not be
available if a large number of cases are considered in a batch run. The user should run an input file with a small
number of cases to ensure that the "house-keeping" is proper.
The following steps are required for a batch run of DCAL:
1. Using an editor (e.g., Windows NOTEPAD) create a batch input file with extension INP in the work
folder of choice. This file can be constructed by editing the file EXAMPLE.INP provided in the work
folder work2.
2. Click on the DCAL icon on the desktop to obtain the DCAL main menu. Determine whether the work
folder indicated on the bottom line of the screen is the desired folder. If not, press and select the
appropriate folder.
3. Select "DBATCH" from the menu or press . A list of batch input files (extension INP) in the active
work folder will appear. Select the appropriate batch input file using the arrow keys. Press . The
calculations will then begin. When the calculations are complete the following message will appear:
Batch calculations are complete.
Press any key to return to menu.
The output of the batch run will be found in the work folder in which the batch input file resides (see Step 2).
The output files use the root name of the batch input file (e.g., EXAMPLE) and include the log file (extension
OUT). Output dose files will have extension GDB, HDB, or JDB, where the first letter G, H, or J represents
ingestion, inhalation, or injection, respectively. If you choose to calculate risk coefficients, then risk files with
extensions RBS and TAB will be generated. The file with extension RBS contains age- and gender-specific and
total estimates of radiogenic mortality and morbidity by cancer site. The file with extension TAB contains
summary risk estimates for the population in the form of a mortality risk coefficient and a morbidity risk
coefficient for all radiogenic cancers combined. Files with these extensions should not be deleted during the
course of the calculations. An example batch input file is shown in Fig. 6.1.
37
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DCAL example batch input file for inhalation.
******* nn s ffffffff ffffffff aaaa
t 1.0E-02 ffffffff <-- Comments >
BATCH CODES
<- List of codes to run in batch
ACTACAL.EXE
SEECAL.EXE
EPACAL.EXE
RISKCAL.EXE
END CODES
<- End of listing of codes
DELETE CASE FILES
<- List of case files to deleted
* . SEE
* .REQ
* .LOG
* .ACT
* . HRT
* . DRT
END DELETE
<- End of case files to deleted.
GLOBAL INPUT
<- Start of global input for cases
Dose Type Absorbed Dose
Intake Route Inhalation
Exposure Type Environmental
Default Amad 1.0
# Ages at intake 6
100 365 1825 3650 5475 7300
END GLOBAL INPUT
<- End of global case input
CASE INPUT DATA
<- Start of case data
H-3 H H20
V H20Vapor
H-3 H H20
G HGas
Be-7
F 1.0
Be-10
F 1.0
C-14 C Org
F 1.0
C-14 C C02
G C02GAS
Na-22
F
Mg-28
M
P-32
F
S-35 S Inorg
F
S-35 S Inorg
V S02Gas
S-35 S Org
V CS2Gas
END CASE DATA
<- End of case data
Format information:
******* nn s ffffffff ffffffff aaaa
1 1 1 1 1 1
1 1 1 1 1 1
1 1 1 1 1 1
t 1.0E-02 ffffffff <-- Comments >
| | | lung file
| | AMAD (micron)
| absorption type
1 1 1 1 1 1
adult age <> global value
| | | | | special
fl file
| III special biokinetic file
| | | (S)hared or (I)ndependent kinetics, default S
| | index of last chain member, default by ACTACAL's procedure
1 nuclide
Fig. 6.1. Illustration of a DCAL batch input file. The user may create a batch file by editing this file
(found in the work2 folder). This is an example DCAL batch input file for inhalation cases.
38
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In the sample input file shown in Fig. 6.1, the first line is a general description of the file:
DCAL example batch input file for inhalation.
The ne\l line shows llie sliucluiv of llic nuclide-s|vcilic dala iji\en laler in llie lilc under '( ASL INIHFT
DMA"
******* nn S ffffffff ffffffff aaaa t 1.0E-02 ffffffff <-- Comments >
The structure (data format) is defined at the end of the sample input file.
Between the delimiters BATCH CODES and END CODES, the user lists the computational modules (codes) to
be run in the batch mode. Available modules are summarized in Section 3. If only activity calculations are
needed, list only the file ACTACAL.EXE. If absorbed dose or equivalent dose estimates are needed, list
ACTACAL.EXE, SEECAL.EXE, and EPACAL.EXE; the choice of absorbed dose or equivalent dose is
specified later in the input stream. To calculate risk coefficients, list those three files and also RISKCAL.EXE
(as shown below), and later in the input stream choose the absorbed dose option. For each case input defined
under CASE INPUT DATA, the specified sequence of computational modules will be executed.
BATCH CODES
<- List of codes to run in batch
ACTACAL.EXE
SEECAL.EXE
EPACAL.EXE
RISKCAL.EXE
END CODES
<- End of listing of codes
Next, between the delimiters DELETE CASE FILES and END DELETE, list the extensions of the files
generated by the sequence of computational modules (codes) that you do not want to retain. The output files
that will be generated depend on the codes selected in the previous step. DCAL output files are described in
Section 3. The inclusion of an extension for a file that was not generated does not result in an error.
DELETE CASE FILES
<- List of case files to deleted
* . SEE
* .REQ
* . LOG
* .ACT
* . HRT
* . DRT
END DELETE
<- End of case files to deleted.
The remaining portion of the input file consists of two data blocks, the "global" data block and the case-specific
data block. The global data block is bounded by the delimiters GLOBAL INPUT and END GLOBAL INPUT.
The statements must appear in the order shown. The global block indicates:
• the type of dose to be computed (Equivalent Dose or Absorbed Dose);
• the intake route;
• for inhalation, the type of exposure (environmental or occupational);
• for inhalation, the default particle size (AMAD);
• the number of ages at intake to be considered;
• a list of the ages to be considered.
39
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The case-specific input data are bounded by the delimiters CASE INPUT DATA and END CASE DATA. The
format of the case input records is given at the top of the file and again near the bottom of the file, and is
explained at the bottom of the file. Case-specific input consists of the following:
• the name of the radionuclide;
• the length of the decay chain to be considered (if not provided, ACTACAL will decide);
• the assumption concerning the biokinetics of decay chain members (S for shared kinetics and I for
independent kinetics; if not provided, shared kinetics is assumed);
• the name of the radionuclide's biokinetic file (required only if a file different from the file X.DEF or
XX.DEF is to be used, where X or XX is the symbol for the element);
• the name of the radionuclide's f file (required only if a file different from the file X.GF 1 or XX.GF1 is
to be used, where X or XX is the symbol for the element);
• the intake age of the adult if different from the global value;
• if intake is by inhalation, the behavior of the aerosol (absorption type);
• if intake is by inhalation, the type of exposure (occupational or environmental) and AMAD must be
indicated if different from the global value;
• if intake is by inhalation and special assumptions are to be made regarding the respiratory kinetics of a
radionuclide, the name of the lung file describing the special kinetics.
If DCAL encounters a problem in the batch input data file, the calculations for that case are terminated and the
next case is considered. The batch log file (extension OUT) should be consulted regarding possible aborted
cases. Limited information is available in the batch mode to diagnose the cause of an aborted case. Attempting
to process the aborted case in the interactive mode may reveal the problem.
The use of the INI files of the computational modules, located in the INI folder, in the batch mode is the same as
in the interactive mode. That is, if the INI file is present in the folder with the batch file (the * .INP file) being
processed, that local INI file is used rather than the global file in the INI folder.
An annotated set of files created during batch the calculation of age-specific dose and risk coefficients can be
found in Appendix B
40
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7.0 CREATING ADDITIONAL BIOKINETIC FILES
You can form your own biokinetic library by copying or creating systemic biokinetic files (file extension name
DEF) and f] files (file extension name GF1) and adding them to a biokinetic folder that you have created or to
the folder \DCAL\DAT\BIO\USR created during installation of DCAL. The purpose of this Section is to
describe the form and content of the DEF and GF1 files.
7.1 FORM OF A DEF FILE DESCRIBING A SYSTEMIC BIOKINETIC MODEL
DCAL requires that the kinetics of materials in the body be described in terms of compartment models with
first-order transfers between compartments. Transfer coefficients of a model are allowed to vary with age.
Transfer coefficients are specified in the DEF file for up to 10 selected ages, and DCAL interpolates linearly
with age to derive age-specific coefficients for intermediate ages. Coefficients for the lowest selected age are
assigned to lower ages, and coefficients for the highest selected age are assigned to higher ages.
A DEF file describes a systemic biokinetic model for an element, representing either a parent radionuclide or a
subsequent decay chain member. As an illustration, the DEF file corresponding to the ICRP's systemic
biokinetic model for iodine in the worker (ICRP Publication 68, 1994b) is given below. As in all of DCAL's
DEF files, the transfer coefficients are in units of d"1.
File I.DEF, iodine biokinetics, ICP.P Pub. 68
1 : Number of age groups
File checked or updated by KFE, 5/2/2006.
Iodine kinetics
7300 Adult
Blood
->Thyroid
8.3178E-01
Blood
->UB Cont
1.9408E+00
Thyroid
->Other
8.6643E-03
Other
->Blood
4.6210E-02
Other
->ULI Cont
1.1552E-02
EOF Data
Notes:
UB Cont is urinary bladder contents
ULI_Cont is upper large intestine contents
This biokinetic file for iodine consists of the following:
Line 1: Title or description of file.
Line 2. format (14): Number of age groups, i.e., ages at which transfer coefficients are specified.
Lines 3-5: Additional text, intended to allow more extensive description or documentation of the file.
Next N lines. N < 11. format (I5.lx.A8'): The N selected ages (in days) in increasing order, and (optional)
descriptive names for these age groups at which the biokinetics will be specified. For example, if ages 100 and
7300 d are selected and the descriptive names are "3-mo-old" and "Adult", respectively, the next two lines
would read:
100 3-mo-old
7300 Adult
41
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Remaining data lines, format (A10.2x.A10. KHIPEI 1.4)): Complete set of systemic transfer coefficients
between compartments of model consisting of name of donor compartment X, name of receptor compartment Y,
and N transfer coefficients (units of d"1) from X to Y for N selected age groups in order of increasing age.
Last required line, format (A 10): Consists of "EOF Data", to denote that the data have been completely
specified. Notes may be added after this line, as indicated in the example.
Another sample DEF file, this one with age-dependent transfer coefficients, is shown below. This file shows the
age-specific biokinetic model for iodine used in the ICRP's series of documents on doses to members of the
public from intake of radionuclides (ICRP 1989, 1993, 1995b, 1996). With regard to the adult, this DEF file is
identical to the previous file representing the systemic biokinetics of iodine in the worker.
File I.DEF, age-specific biokinetics of iodine, ICP.P Pubs 56, 67, 71, 72
6 : Number of age groups
File checked or updated by KFE, 8/13/95.
Iodine kinetics
100 3 mo-old
365 1 y-old
1825 5 y-old
3650 10 y-old
5475 15 y-old
7300 Adult
Blood ->Thyroid 8.3178E-01 8.3178E-01 8.3178E-01 8.3178E-01 8.3178E-01 8.3178E-01
Blood ->UB_Cont 1.9408E+00 1.9408E+00 1.9408E+00 1.9408E+00 1.9408E+00 1.9408E+00
Thyroid ->Other 6.1888E-02 4.6210E-02 3.0137E-02 1.1951E-02 1.0345E-02 8.6643E-03
Other ->Blood 4.9511E-01 3.6968E-01 2.4109E-01 9.5606E-02 8.2764E-02 4.6210E-02
Other ->LI_Cont 1.2378E-01 9.2420E-02 6.0274E-02 2.3902E-02 2.0691E-02 1.1552E-02
EOF Data
Notes:
UB_Cont is urinary bladder contents
ULI_Cont is upper large intestine contents
In the DEF files, the names of donor and receptor compartments must correspond to DCAL-standardized names
of anatomical regions of the body representing source regions in dosimetric calculations. The naming
convention used in DCAL for source regions and compartments of biokinetic models is described in Section 3,
and standard names of source regions are listed in Table 3.1 of that chapter. Briefly, in order for DCAL to
relate the biokinetic compartments to standard source regions used in radiation dosimetry, the name of a
compartment of a biokinetic model must be an extension of the standard name of a source region. For example,
if the liver is an explicitly defined source region in a systemic biokinetic model, then DCAL assigns the activity
in compartments beginning with the name "Liver" to the source region Liver. The name of a compartment
within the liver could be "Liver" or could be of the form "Liver_X", where the symbol "_X" represents a
subscript and X can be any number or letter. The underscore character is required to identify a subscript. See
Section 3.5 for additional discussion. Up to 15 compartments are allowed for a given source region.
7.2 SPECIAL CONSIDERATIONS FOR NAMING COMPARTMENTS USED TO DESCRIBE
CIRCULATION OR EXCRETION OF MATERIAL
A compartment within blood must be of the form "Blood" or "Blood X". At least one "Blood" compartment
must be included in the data files describing the kinetics of the systemic materials.
Material that leaves the systemic circulation via urinary excretion should be transferred to the compartment
named "UB_Cont" if a dose estimate for the urinary bladder (UB) is to be developed. Similarly, systemic
42
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material lost through fecal excretion should be transferred to either the "SI_Cont" or "ULICont" compartment
of the gastrointestinal tract. Part of any material routed through " SICont" will be lost through fecal excretion
at a rate indicated by the gastrointestinal tract model of ICRP Publication 30 (1979), but a fraction (/i) will be
absorbed back into the systemic circulation. Reabsorption of material to blood can be avoided by routing the
fraction of outflow from blood intended for fecal excretion directly into the "ULI Cont" compartment.
If the biokinetic model indicates that material is lost from the systemic circulation by an unspecified excretion
route, or if the specified route of excretion is not used in dosimetric calculations (e.g., hair or sweat), then the
transfer should be specified to a compartment labeled "Excreta". The compartments "Excreta", "Urine", and
"Feces" exist outside the body and do not enter into dosimetric calculations. The "Urine" and "Feces"
compartments are reached by material that has first been transferred to compartments representing the urinary
bladder contents or contents of the intestines.
7.3 FORM OF A GF1 FILE DESCRIBING FRACTIONAL UPTAKE FROM THE
GASTROINTESTINAL TRACT
Absorption of material from the gastrointestinal tract to blood is represented as occurring in the small intestine.
Fractional absorption from the small intestine to blood is described by an f value. A file with extension GF1 is
a list of age-specific f\ values and the corresponding ages, in days. As is the case for transfer coefficients, f
values for intermediate ages are determined in DCAL by linear interpolation.
A GF1 file for an element consists of the following:
Line 1: Title or description of file.
Line 2. format (14): Number of age groups, i.e., ages at which transfer coefficients are specified.
Lines 3-5: Additional text, intended to allow more extensive description or documentation of the file.
Each of next N lines. N < 11. format - free form: N age-specific f values and corresponding age groups. Each
line contains an f value and the corresponding age group (in days), separated by space or comma.
Three sample GF1 files are shown below. The first sample file gives the ICRP's f| value for iodine in adults.
The second sample file specifies the same/J value but at age 100 d, indicating that this value is applied to all age
groups starting at 100 d. The third sample file gives the age-specific f values for Sr specified in ICRP
Publication 67 (1993), i.e., 0.6 in the infant (100 d), 0.4 at age 365 d (1 y), 0.4 at age 5475 d (15 y), and 0.3 for
age 9125 d (definition of adulthood for strontium biokinetics) and higher.
43
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File I.gf1, GI uptake of iodine by a worker (ICRP Pub.
68)
1 : Number of age groups
File checked and/or updated by KFE, 5/2/2006.
Age-specific fl values for ingested or inhaled (Type F)
iodine.
i n iinn
File I.gf1, age-specific GI uptake of iodine (ICRP Pubs. 56, 67)
1 : Number of age groups
*****+**+**+**+*****+**+**+**+********+**+**
File checked and/or updated by KFE, 5/2/2006.
Age-specific fl values for ingested or inhaled (Type F) iodine.
1.0 100
File Sr.gfl, age-specific GI uptake of strontium (ICRP Pub. 67)
4 : Number of age groups
******+**+**+**+**+**+**+*****+**+*****+****
File checked and/or updated by KFE, 5/2/2006.
Age-specific fl values for ingested or inhaled (Type F) strontium,
n p. inn
The f values are implemented in DCAL in terms of a transfer coefficient from the small intestine (SI) contents
to blood. This coefficient is set to give the proper fractional transfer from SI contents to blood, considering that
this transfer is in competition with transfer at a rate of 6 d"1 from SI contents to upper large intestine contents.
The transfer coefficient from SI contents to blood is interpolated linearly with age to account for changes with
age in f values. With regard to f values given in the sample file for Sr, the transfer coefficient from SI contents
to blood would remain constant between ages 365 d and 5475 d because the f value is 0.4 at each end of this
age interval; however, this transfer coefficient would decrease with age between ages 5475 d and 9125 d
because the f value decreases from 0.4 at age 5475 d to 0.3 at age 9125 d. The f value 0.3 for Sr assigned to
age 9125 d applies to all higher ages, so that the transfer coefficient describing the rate of movement of Sr from
SI contents to blood would not change after age 9125 d.
7.4 CREATING DEF or GF1 FILES BY COPYING AND EDITING AN EXISTING FILE
The folders \DCAL\DAT\BIO\F13 and \DCAL\DAT\BIO\I68 contain files representing systemic biokinetic
models (extension DEF) or f values (extension GF1). The easiest method of creating a new DEF or GF1 file
usually is to locate, copy, and edit a similar file found in one of these two folders. The copied and edited file
should be saved in a biokinetic folder other than \DCAL\DAT\BIO\F 13 or \DCAL\DAT\BIO\I68, i.e., either in
the folder \DCAL\DAT\BIO\USR created when DCAL is installed, or in a biokinetic folder that you have
created.
As an illustration, suppose you want to estimate thyroid dose from ingestion of 131I by an adult based on a
biological half-time in the thyroid that is half as large as that assumed by the ICRP. An easy way to do this is to
copy the file I.DEF in \DCAL\DAT\BIO\I68 (the first sample file shown in this section) to a selected biokinetic
folder and modify the transfer coefficient in the following line:
44
-------
Thyroid ->Otlier 8.6643E-03
The transfer coefficient 8.6643E-03 (d1) used in ICRP Publication 68 corresponds to a biological half-time of
80 d, i.e., ln(2)/(80 d) = 8.6643 d"1. Replace 8.6643E-03 with the value 1.7328E-02 d"1 (=ln(2)/40 d), save the
edited file as I.DEF in the selected folder, and run DCAL with that folder selected as the active biokinetic folder
to get dose estimates for ingested 131I in the adult based on a 40-d biological half-time in thyroid.
45
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8.0 THE METHOD USED BY ACTACAL TO SOLVE BIOKINETIC MODELS
8.1 BACKGROUND
Many of the biokinetic models for radionuclides currently used by the ICRP depict continual redistribution of
activity among a large number of compartments at rates that vary with age. Some applications of these models
give rise to large and complicated systems of differential equations representing the time-dependent activity in
different organs of the body. This is particularly true when these models are used in conjunction with the
assumption of independent kinetics of radioactive progeny. As one example, application of the ICRP's current
models and assumptions (ICRP, 1994a, 1995a) to the case of inhalation of 232Th by a child requires solution of a
first-order model involving about 400 compartments, feedback of activity between compartments, and transfer
coefficients that vary with age and hence time. The large number of compartments stems from the fact that each
compartment of the ICRP's respiratory tract model (with numerous compartments), gastrointestinal (GI) tract
model, and systemic biokinetic model for thorium (also having several compartments) must be viewed as 11
"layers" of compartments, with different layers corresponding to different members of the 232Th chain.
Most techniques for solving compartmental models cannot be applied to such large and complicated systems
due to some combination of the following difficulties: prohibitive time requirements; limitations on the number
of compartments; instability or poor accuracy; and inability to solve models with time-varying coefficients.
Some workers have been able to solve such models using sophisticated solvers, but large amounts of system
resources and computing time are required.
The solver used in ACTACAL is an elementary approximation technique developed and refined by ORNL's
dosimetry team. The technique is particularly well suited to the type of physiologically-detailed biokinetic
models now coming into use in radiation protection, nuclear medicine, and chemical risk analysis. The
technique applies to models with time-dependent transfer coefficients and recycling of material between
compartments and has no restrictions of practical importance on the number of compartments, the network of
flows between compartments, the number of radioactive daughter products, and the paths of movement of
daughter products. For a specified level of accuracy, computing time and storage requirements increase roughly
in proportion to the number of compartments in the model. For most other techniques, these quantities increase
with the square, and sometimes the cube, of the number of compartments or equations involved (Leggett et al.,
1993).
8.2 DESCRIPTION OF THE METHOD
In the following, the term "transfer coefficient" will be used to indicate fractional transfer per unit time from one
compartment to another.
The objective is to estimate the time-dependent inventory of compartments of a first-order model. The
computational method relies on replacement of a relatively complex, exact mathematical formulation of a first-
order compartmental model with a relatively simple, approximate mathematical formulation. A first-order
compartmental model usually is viewed mathematically as a system of first-order differential equations. With
the present approach, the model is viewed as a series of isolated compartments and the time period of interest is
viewed as a series of time steps, and the content of each compartment at the end of each time step is estimated
by applying a simple linear differential equation.
If one assumes first-order kinetics in an isolated compartment that has a constant inflow rate P, a constant
transfer rate coefficient R describing outflow, and an initial activity Y„ at time 0, the activity Yat time T is given
46
-------
dY
by the solution of the differential equation — = -RY + P, namely:
dT
riro-jyRT+j <8i)
The integrated activity YINT from time 0 to time T is then
l-e-RT ( p\ PT
YINT = ^r[r°-R J + ir- (82)
Although these equations do not apply directly to first-order compartmental models involving recycling or
variable transfer coefficients, they may be applied iteratively to approximate the solutions of such models to any
desired degree of accuracy.
The calculation proceeds in a series of time steps measured in days, with the kth step defined by a starting time
Tk and an ending time Tk+1 >Tk. Compartments are numbered 1 through NC. The activity Y(i) in compartment /'
at time Tk , is calculated from Eq. 8.1 by initializing time 0 to Tk, defining the initial activity in the compartment
to be the activity calculated at the ending time in the preceding time step, and replacing T with Pk+1 - Tk. The
integrated activity YINT(i) in the compartment during the same time interval is calculated similarly using Eq.
8.2. During each time step the inflow rate P is taken to be the constant value that would yield the total activity
that flows out of all feeding compartments with lower numbers during the same time step, plus that flowing out
of all feeding compartments with higher numbers during the previous time step. That is, the inflow rate Pi into
compartment /' during the Mi time step is
•jCRQ.DYmro)
' j-1 (Tk+1 - Tk>
where R(j, i) is the transfer coefficient (fractional transfer per day) from compartment j to compartment /' (or
zero if there is no flow from j to /') at the midpoint of the time step and YINT(j) is the last-computed integrated
activity in compartment j. Thus, Y1NPQ) represents the integral from Pk_i to Tk if /' < j or from I'k to Pk+1 if /' > j.
The procedure is repeated until all times of interest have been reached.
In the case of age-specific biokinetic models, it is common practice to specify transfer coefficients for a small
set of "basic" ages, A(]!•'., < AGE2 < ... < AGElast, and to assign coefficients at intermediate ages by
interpolating linearly with age (ICRP, 1989). Suppose, for example, that calculations for acute intake at age
A GUN/ have been made up to time ti and that t2 is the right endpoint of the next time step. Parameter values
for the time step are based on the age of the exposed person at the end of the time step, AGEINJ + t2. If this age
is less than or equal to AGEh transfer coefficients for A (]!•'., are used during the time step, and if this age is
AGELASt or greater, transfer coefficients for AGELAST are used. Otherwise, one selects the smallest k such that
AGEk _ AGEINJ 12 < AGEk+h assigns transfer coefficients fox AG l'JN.I 12 by linearly interpolating input data
for ages AGEk and AGEk+1, and applies the interpolated data to this entire time step.
The following FORTRAN code fragment illustrates how calculations could be performed over a single time step
of length P for compartment /' of an age-specific biokinetic model with NC compartments and with recycling
among compartments:
47
-------
YO = Y(I)
P = 0. 0
R1 = 0.0
DO J=1,NC
P = P + R(J,I) * YINT(J) / T
R1 = R1 + R(I,J)
END DO
Y (I) = (YO - (P/Rl) )EXP(-R1*T) + P/Rl
YINT(I) = ((1.0 - EXP(-R1*T)) / R1)(Y0 - (P/Rl)) + P*T / R1
In the above code fragment, YO, P, Y, and YINT are as defined earlier, and R(J,I) is the interpolated age-specific
transfer coefficient from compartment J to compartment I. If there is radiological decay of material, then a
radiological decay rate must be added to the total biological removal rate from compartment I.
This code fragment represents the central idea of the solver used in ACTACAL. Of course, this code segment
had to be expanded considerably in ACTACAL in order to maximize computing efficiency and deal with such
problems as significance, division by zero, interpolation of transfer coefficients, time steps of variable length,
and growth and potential migration of radioactive progeny.
The computation loops through the indicated calculation once for each compartment in each time step. Due to
the simplicity of the calculation, it is possible to loop through thousands of time steps per second using current
PCs.
8.3 SOURCES AND SIZES OF ERRORS
At the end of each time step, the calculated sum SC of the contents of all compartments of a recycling model,
NC
SC=^Y(i) (8.4)
i=l
usually is a slight underestimate of the activity in the system because there is a delay of one time step in flow
from compartments with higher numbers to compartments with lower numbers. Thus, in a step of length T,
there is an "upward recycling error", URE, in the total system given by
URE = I RQJ) . Y1NTQ)
j>i ^ ¦ >
where YINTQ) is the integrated activity in compartment j during the same step. It is easy to show that the
upward recycling error at the end of a time step of length T is no larger than T-RMAX, where RMAX is the
largest sum of transfer coefficients R(j, i) out of any one compartment j (assuming a unit amount in the system):
NC
RMAX = max £ R (j, i) (8 6)
j i=l
In recycling models representing systemic biokinetics of radionuclides, the upward recycling error may be
orders of magnitude smaller than T -RMAX. The error depends on the number of compartments in the system,
the way in which the substance is distributed among compartments, and the way in which the compartments are
numbered. In any case, the upward recycling error can be reduced to a negligible amount by selection of
sufficiently small time steps.
Errors are also associated with approximation of non-constant inflow rates and variable transfer coefficients by
constants over each time step. These averaging errors can also be reduced to negligible amounts by using
sufficiently small steps. It is difficult to find tight bounds on the propagation of this error over several time
steps, but the averaging error in any single time step is bounded above by (T -RMAX)2. The averaging error
usually produces slight overestimates of the activity in compartments.
48
-------
For biokinetic models of various levels of complexity, we have checked estimates derived by our method
against exact solutions obtained by methods described later, isolated the averaging errors and the upward
recycling errors, and compared the total shortfall and the upward recycling error. We have found that the
upward recycling error usually is the dominant error in recycling models and that the total shortfall error
generally differs little from the upward recycling error. After several time steps, the upward recycling error
becomes distributed among compartments roughly in proportion to the true compartment contents, so that the
total shortfall error is a useful indicator of the relative error in each compartment. For example, if it is required
that estimates be accurate within 0.5% for all compartments at all times, then time steps are chosen so that the
total shortfall is always substantially less than 0.5% of the amount in the system.
8.4 SCHEMES FOR SELECTING TIME STEPS
There are two main criteria for selection of time steps. First, the steps should be sufficiently short that errors
remain within a prescribed limit. Second, times for which estimates are desired should be included in the time
grid defining the steps, since computations are made only at the endpoints of time steps. Alternatively,
estimates for times of interest could be linearly interpolated or otherwise extrapolated from calculations made
for the right endpoints of time steps, but this introduces additional error.
The simplest approach, though usually not the most efficient one, is to maintain a fixed step length throughout
the calculation. In practical applications of ACTACAL, it usually suffices to estimate time-dependent
compartmental activities within a few tenths of a percent. This level of accuracy is usually obtained if one uses
steps of length 10~N d, where N is the smallest positive integer TV such that 10~N+1 < ln(2)/RMAX. If only crude
estimates are desired, one might use steps of length 10~N+1 dor 1 (Fx d, for example. When a given time step is
maintained, the upward recycling error gradually disappears in the frequently encountered case in which a large
portion of the material in the system builds up in compartments with low turnover or goes to excretion. In this
case, if one is interested only in compartment contents at times remote from exposure (say 20 y or 50 y), then
very large time steps (say, 10 d) could be applied.
Except perhaps for batch runs involving hundreds or thousands of cases, computing time generally is not an
important consideration when solving current biokinetic models by this method due to the high speed of current
desktop computers. If computing time does become an important consideration, it can be reduced considerably
by varying the lengths of the steps to reflect changes with time in the rate of relocation of material in the system.
For example, for consideration of an acute intake at time 0, accurate estimates may require relatively short steps
for the time soon after intake, when contents of some compartments may be changing rapidly, but it may suffice
to use longer steps at times remote from intake, when compartmental contents typically are changing more
slowly. The following generic scheme suffices for most purposes:
(a) The smallest positive integer N is found such that 10~N+1 < ln(2)/RMAX, where RMAXis
the highest sum of fractional outflow rates from any compartment in the system.
(b) The following time steps are used: 1000 steps of length 10~N d (taking the calculations
from 0 to 10~N+S d), 900 steps of length / (f': 1 d (taking the calculations from / (f ': 3 to
10~N+4 d), 900 steps of length 10~N+2 d, and so forth, until 100 d is reached; then steps of 1
d until 4000 d is reached; and steps of 10 d thereafter.
This scheme produces desirable endpoints of time steps, typically yields accuracy well within 0.5% even when
step lengths reach 10 d, and requires relatively little computing time.
The default time-stepping scheme used in ACTACAL is the generic scheme described above with N= 3, i.e.,
1000 steps of length 0.001 d, 900 steps of length 0.01 d, 900 steps oflength 0.1 d, 3900 steps oflength 1 d, and
2155 steps of length 10 d, giving a total of 8855 steps to reach 70 y (25,550 d) from time of intake. Directions
for changing the time-stepping scheme in DCAL are given in a later section.
49
-------
The default scheme used in ACTACAL was based on consideration of the largest transfer coefficient occurring
in most of the models of ICRP Publication 68 (1994b) and the ICRP's series of documents on age-dependent
doses to members ofthe public from intake of radionuclides (ICRP 1989, 1993,1995a, 1995b, 1996). Although
transfer coefficients in those models occasionally do not satisfy item (a) above, we have found that the default
scheme produces suitable approximations for the applications in radiation protection to which DCAL is
expected to be applied. A much coarser time grid would work for most applications of DCAL, particularly
applications to biokinetic models that do not involve recycling of material. Because the present scheme is
already reasonably time-efficient, however, the time saved by changing to an optimal scheme for a new
application of DCAL would usually be more than offset by the time required to edit the file.
8.5 COMPARISONS WITH OTHER SOLVERS
Numerous checks of the accuracy of this method have been made through comparison of solutions of this and
other solvers for a variety of biokinetic models. For some relatively simple models, it is possible to solve the
models in closed form and thus produce exact solutions that may be checked against ACTACAL's solutions. For
example, the ICRP's current model for movement of material through the segments of the GI tract (ICRP
Publication 30, 1979) can be solved in closed form. Comparisons of ACTACAL estimates with exact
calculations of contents of segments of the GI tract were made for different times following acute ingestion of 1
Bq of a long-lived radionuclide, assuming no absorption to blood (Table 8.1). ACTACAL estimates generally
agree with the exact solutions through five significant digits except at very early times (0.01 d in this table), for
which disagreement in the third or fourth significant digit is seen for upper and lower large intestines. As a rule,
the largest relative errors produced by ACTACAL occur in the first few time steps (10 steps were needed here
to reach 0.01 d) or immediately after an increase in the step size.
Many comparisons have been made with published tables of nuclear transformations over 5 0 y in source organs,
based on the models of ICRP Publication 30 (1979). These tables are found in the supplements to that
document and were produced by the code TIMED, which was formerly used at ORNL and which incorporates a
widely used adaptive predictor-corrector solver. While these comparisons have shown excellent agreement
between TIMED and ACTACAL, this is not a strong test of ACTACAL because the models of ICRP
Publication 30 generally are not complex and the tables in the supplements to Publication 30 provide only two
significant digits.
Checks on the accuracy of ACTACAL's solutions of the recycling models appearing in the ICRP's series of
documents on doses to the public from intake of radionuclides (ICRP 1989, 1993, 1995a, 1995b, 1996) have
been made through comparisons with two virtually exact solvers with regard to the relatively "non-stiff' models
of this series: a computer code called DIFSOL, which obtains analytical solutions of linear ordinary differential
equations with constant coefficients (Killough and Eckerman 1984); and a computer code developed by Birchall
and James (1989) for solving first-order compartmental models with recycling but with constant transfer
coefficients. DIFSOL is built around routines from EISPACK (Smith et al. 1974), a sophisticated software
collection for eigensystem analysis.
To check ACTACAL solutions of age-dependent biokinetic models, we developed a computer code based on
the algorithm developed by Birchall and James (1989) but allowing time-dependent transfer coefficients.
Essentially, the Birchall-James algorithm is "stepped" in the same way as in our method. Errors are controlled
by controlling the step size. This method has the advantage that it involves only one of the relatively minor
sources of error associated with our method, namely, that of approximating variable transfer coefficients by
constants over short time steps. Virtually exact solutions can be obtained by making successive computer runs
and shrinking the step sizes until convergence is reached. The method has the distinct disadvantage, however,
that computing time increases with the cube of the number of compartments. This prohibits application to
50
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biokinetic models for parent radionuclides that give rise to long chains of radionuclides.
Comparisons of the DCAL solver with the various methods summarized above are illustrated in Tables 8.2-8.4.
The comparisons in Table 8.2 are for the iodine model used in ICRP Publication 56 (1989) (the DEF file is
shown in Section 7.1), assuming acute intake to blood of an adult and no radiological decay of iodine. Four
different time-stepping schemes were used in ACTACAL to illustrate the increased accuracy with decreasing
step sizes. In three cases, fixed time steps (1 d, 0.1 d, or 0.01 d) were used. In the fourth case, DCAL's default
time-stepping scheme was used. The exact solution was produced by DIFSOL and checked using the Birchall-
James code.
The comparisons in Table 8.3 are for the same iodine model, but in this case it is assumed that acute intake to
blood occurs at age 1 y. Thus, in this case the transfer coefficients are age dependent. The exact solution to
four significant digits was produced by our modified Birchall-James method. That is, time-steps were decreased
until convergence through four digits was achieved. Three different time-stepping schemes were used to
produce the three sets of ACTACAL estimates: fixed time steps of 0.1 d, fixed time steps of 0.01 d, and the
default time-stepping scheme.
The comparisons in Table 8.4 are for the age-specific biokinetic model for americium used in ICRP Publication
67 (1993). Compartments and paths of movement in the model are shown in Fig.8.1, and the DEF file
representing the model is given in Table 8.5. For ages intermediate to those indicated in Table 8.5, transfer
coefficients are defined by linear interpolation, as described earlier. The estimates in Table 8.4 are for the case
ofinjection of "stable" Amatage 1 y. Comparison is made with the modified Birchall-James method based on
time steps of 1 d. It appeared that convergence of the modified Birchall-James method through at least three
digits had been attained when time steps were no greater than 1 d. For models involving 20 or more
compartments, application of the Birchall-James method would require considerable computing time on a
relatively fast desktop computer to reach a time of several thousand days by using time steps substantially
shorter than 1 d.
51
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Table 8.1. Comparison of ACTACAL estimates with exact calculations (closed form
solution) of contents of segments of the gastrointestinal tract at times following acute
ingestion of 1 Bq of a very long-lived radionuclide, based on the ICRP's gastrointestinal tract
model.
Method
Time (d)
Stomach
Small
Upper large
Lower large
intestine
intestine
intestine
ACTACAL
7.8663E-
2.0685E-
6.4807E-
3.9992E-05
Exact
0.01
01
01
03
3.9833E-05
solution
7.8663E-
01
2.0685E-
01
6.4833E-
03
ACTACAL
9.0718E-
6.1080E-
2.7732E-
2.0567E-02
Exact
0.1
02
01
01
2.0567E-02
solution
9.0718E-
02
6.1079E-
01
2.7733E-
01
ACTACAL
8.2297E-
3.9062E-
5.0675E-
8.8629E-02
Exact
0.2
03
01
01
8.8628E-02
solution
8.2297E-
03
3.9062E-
01
5.0675E-
01
ACTACAL
6.1442E-
6.6375E-
5.3308E-
3.3018E-01
Exact
0.5
06
02
01
3.3018E-01
solution
6.1442E-
06
6.6375E-
02
5.3308E-
01
ACTACAL
3.7751E-
3.3050E-
2.5057E-
4.6376E-01
Exact
1.0
11
03
01
4.6376E-01
solution
3.7751E-
11
3.3050E-
03
2.5057E-
01
ACTACAL
0.0
8.1924E-
4.2187E-
2.8635E-01
Exact
2.0
0.0
06
02
2.8635E-01
solution
8.1923E-
06
4.2187E-
02
ACTACAL
0.0
1.2477E-
1.9060E-
1. 8555E-02
Exact
5.0
0.0
13
04
1.8555E-02
solution
1.9059E-
04
ACTACAL
0.0
0.0
2.3521E-
1.2786E-04
Exact
10.0
0.0
0.0
08
1. 2786E-04
solution
2.3521E-
08
52
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Table 8.2. Comparison of estimates based on our method with exact solutions, applied to a
biokinetic model for iodine (ICRP 1989), assuming intake to blood of an adult
and no radiological decay
Stepping
scheme
Contents (fraction of intake to blood)
Blood
Thyroid
Other
Cumulative
Urine
Cumulative
Feces
At 1 d:
Fixed (1 d)
Fixed (0.1 d)
Fixed (0.01 d)
Default
Exact solution3
0.6250E-01
0.6251E-01
0.6252E-01
0.6252E-01
0.6252E-01
0.2800E+00
0.2795E+00
0.2795E+00
0.2795E+00
0.2795E+00
0.1180E-02
0.1671E-02
0.1676E-02
0.1676E-02
0.1676E-02
0.6563E+00
0.6563E+00
0.6563E+00
0.6563E+00
0.6563E+00
0.6884E-05
0.7681E-05
0.7703E-05
0.7703E-05
0.7703E-05
At 10 d:
Fixed (1 d)
Fixed (0.1 d)
Fixed (0.01 d)
Default
Exact solution
0.2638E-03
0.2957E-03
0.2979E-03
0.2979E-03
0.2982E-03
0.2774E+00
0.2772E+00
0.2772E+00
0.2772E+00
0.2772E+00
0.1809E-01
0.1838E-01
0.1839E-01
0.1839E-01
0.1839E-01
0.7023E+00
0.7029E+00
0.7030E+00
0.7030E+00
0.7030E+00
0.1095E-02
0.1137E-02
0.1137E-02
0.1137E-02
0.1137E-02
At 100 d:
Fixed (1 d)
Fixed (0.1 d)
Fixed (0.01 d)
Default
Exact solution
0.4307E-03
0.4278E-03
0.4276E-03
0.4278E-03
0.4276E-03
0.1528E+00
0.1527E+00
0.1527E+00
0.1527E+00
0.1527E+00
0.2560E-01
0.2559E-01
0.2560E-01
0.2559E-01
0.2560E-01
0.7881E+00
0.7892E+00
0.7893E+00
0.7892E+00
0.7893E+00
0.3189E-01
0.3198E-01
0.3199E-01
0.3198E-01
0.3199E-01
At 1000 d:
Fixed (1 d)
Fixed (0.1 d)
Fixed (0.01 d)
Default
Exact solution
0.1479E-05
0.1452E-05
0.1450E-05
0.1476E-05
0.1450E-05
0.5219E-03
0.5158E-03
0.5153E-03
0. 5207E-03
0.5152E-03
0.8790E-04
0.8689E-04
0.8679E-04
0.8769E-04
0.8679E-04
0.9206E+00
0.9206E+00
0.9206E+00
0.9206E+00
0.9206E+00
0.7879E-01
0.7879E-01
0.7879E-01
0.7879E-01
0.7879E-01
aExact solution produced by DIFSOL and BIRCHALL methods.
53
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Table 8.3. Comparison with exact solutions of estimates based on our method, applied to an
age-specific biokinetic model for iodine (ICRP 1989), assuming intake to blood at age 1 y
and no radiological decay
Stepping Contents (fraction of injected I)
scheme Blood Thyroid Other Urine Feces
At 1 d:
Default 0.6310E-01 0.2724E+00 0.7551E-02 0.6566E+00 0.2919E-03
Fixed T (0.1 d) 0.6300E-01 0.2724E+00 0.7526E-02 0.6565E+00 0.2910E-03
Fixed T (0.01 d) 0.6310E-01 0.2724E+00 0.7551E-02 0.6566E+00 0.2919E-03
Exact solution3 0.6311E-01 0.2724E+00 0.7551E-02 0.6566E+00 0.2919E-03
At 10 d:
Default
Fixed T (0.1 d)
Fixed T (0.01 d)
Exact solution
0.2991E-02
0.2996E-02
0.2991E-02
0.2990E-02
0.2093E+00
0.2092E+00
0.2093E+00
0.2093E+00
0.2226E-01
0.2225E-01
0.2226E-01
0.2227E-01
0.7476E+00
0.7470E+00
0.7476E+00
0.7476E+00
0.1776E-01
0.1775E-01
0.1776E-01
0.1776E-01
At 100 d:
Default
Fixed T (0.1 d)
Fixed T (0.01 d)
Exact solution
0.1449E-03
0.1450E-03
0.1442E-03
0.1441E-03
0.1016E-01
0.1016E-01
0.1014E-01
0.1013E-01
0.1096E-02
0.1097E-02
0.1094E-02
0.1094E-02
0.9126E+00
0.9126E+00
0.9126E+00
0.9126E+00
0.7597E-01
0.7597E-01
0.7598E-01
0.7598E-01
At 1000 d:
Default 0.3943E-15 0.3455E-13 0.3731E-14 0.9210E+00 0.7895E-01
Fixed T (0.1 d) 0.3024E-15 0.2724E-13 0.2941E-14 0.9210E+00 0.7895E-01
Fixed T (0.01 d) 0.2936E-15 0.2651E-13 0.2862E-14 0.9211E+00 0.7895E-01
Exact solution 0.2927E-15 0.2643E-13 0.2854E-14 0.9211E+00 0.7895E-01
aExact solution produced by modified BIRCHALL method.
54
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Table 8.4. Estimated organ contents (Bq) at different times after injection of americium at
age 1 y, based on the americium model of ICRP Publication 67 (1993) and two different
computational methods"
Method
Time(d)
Skeleton
Liver
Kidneys
Other
Testes
Bi rchallb
1
0.6150
0.08778
0.02049
0.1972
0.000026
ACTACALC
±
0.6149
0.08776
0.02048
0.1972
0.000026
Bi rchal1
1 n
0.7072
0.09942
0.01284
0.0841
0.000030
ACTACAL
±U
0.7071
0.09942
0.01284
0.0841
0.000030
Bi rchal1
1 nn
0.7356
0.09588
0.00525
0.0463
0.000033
ACTACAL
±uu
0.7354
0.09585
0.00525
0.0463
0.000033
Bi rchal1
1 nnn
0.5346
0.13829
0.00551
0.0570
0.000068
ACTACAL
xuuu
0.5332
0.13793
0.00549
0.0568
0.000068
Bi rchal1
1 nnnn
0.1974
0.02684
0.00041
0.1064
0.000249
ACTACAL
xuuuu
0.1969
0.02700
0.00041
0.1061
0.000248
aTo decrease running time for the Birchall method, no gastrointestinal tract compartments were added. Thus,
for purposes of this comparison, the Am model of ICRP Publication 67 was modified to eliminate
reabsorption of a small amount of Am from the gastrointestinal tract to blood.
bAs modified by our group to address age-dependent transfer coefficients.
Using the default time-step scheme. Increased accuracy can be obtained using a finer grid.
8.6 TREATMENT OF DECAY CHAINS OF RADIONUCLIDES
Consider a decay chain of M radionuclides that flow among N compartments. The different members of the
chain may have element-specific transfer coefficients between compartments, or they may be assigned the
transfer coefficients of the parent, as in ICRP Publication 30 (1979). Selection of step sizes is based on the
considerations described earlier in this section, keeping in mind that the highest biological transfer coefficient
(RMAX) in the system could be associated with a member of the chain other than the parent.
Number the chain members so that there is no decay from higher numbered to lower numbered members.
Denote by A(k,i)(t) the activity of chain member /' in compartment k at time I. For a given time step, A (k, 1) at the
right endpoint of the step is calculated as described earlier, using inflow from all compartments that feed chain
member 1 into compartment k. Outflow of chain member 1 from compartment k consists of biological removal
plus radiological decay of chain member 1. For the same time step, A(k,2) is calculated by the method
described earlier, but using an average inflow rate based on inflow from all compartments that feed chain
member 2 into compartment k, plus inflow from compartment k due to radiological decay of chain member 1
during that time step. The calculation is continued through all M members of the chain and then goes to the
next time step. In effect, we are treating the problem as if there is only a single radionuclide flowing among Nx
A/compartments and are handling radiological decay as if it were biological flow from a compartment defined
by a pair (k, i) to a compartment defined by a pair (k, j), where j> i.
Since there is no "upward recycling" of daughter products with this method, the only error associated with
estimation of daughter growth in this way is the relatively small "averaging" error described earlier, that is,
replacement of the time-varying growth of a daughter product with a constant inflow rate on each time step.
Of course, with a recycling model there will be upward recycling errors associated with moving the ingrowing
daughters among compartments according to their given transfer coefficients. Those errors will be controlled as
described earlier by the choice of time steps since the biological transfer coefficients of all members of the chain
55
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are considered when setting the time steps.
Errors involved in estimating growth of daughter products in this way may be checked by comparison of
estimates with results obtained using the Bateman equation. We have found that the error is typically no larger
than 0.2% when the time step is 10 d or less, even for chains with several members whose radiological half-
times differ by many orders of magnitude (e.g., the 226Ra or 228Ra chains).
8.7 HOW TO CHANGE THE TIME STEPS IN DCAL
Y ou can change the time-stepping scheme used to solve biokinetic models by editing the first two lines of the
file timin.dat found in folder \DCAL\DAT\MIS. For the default time-stepping scheme used in DCAL, these
two lines are as follows:
0.0, 0.001, 0.01, 0.1, 1., 10.
8857, 1000, 1900, 2800, 6700
Note that the values are separated by a comma and space.
The first line represents the variables deltO, deltl, delt2, delt3, delt4, and delt5. The variable deltO is set to zero
if increasing time steps are desired. A nonzero deltO overrides subsequent values on this line and assigns
constant step length deltO (days) throughout the calculation. The values deltl, delt2, delt3, delt4, and delt5 are
the first through fifth different step lengths (days) for the case of variable time steps. One need not use all five
step lengths. Whether or not a step length is reached during the calculation depends on the values in the second
line.
The second line represents the variables ncycle, icycl, icyc2, icyc3, and icyc4. The value ncycle is the total
number of steps to be used in the calculation. The values icycl through icyc4 represent the step number at
which the next step length is started when variable step lengths are used. For example, if deltO = 0.0, step
length deltl is used for time steps 1 through icycl - 1, step length deli2 is used for time steps icycl through
icyc2 -1, and so forth.
56
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Table 8.5. The DEF file representing the systemic biokinetic model for americium
used in ICRP Publication 67 (1993).
File am.def
6 : Number of age groups
File checked and/or updated by RWL, 8/10/95
Biokinetics of Am,ICRP 67.
100 Infant
365
1825
l-yr_old
5-yr_old
3650 10-yr_old
5475 15-yr_old
9125 Adult
Blood
Blood
Blood
Blood
Blood
Blood
Blood
Blood
Blood
Blood
Blood
Blood
Liver_l
Liver_l
0ther_0
Other_l
0ther_2
C_Bone-
C_Bone-S
C_Bone-S
C_Bone-V
R_Marrow
T_Bone-S
T_Bone-S
T_Bone-V
Kidneys_l
Kidneys_2
Testes
Ovaries
EOF Data
->Liver_l
->0ther_0
->0ther_l
->0ther_2
->C_Bone-S
->T_Bone-S
->Kidneys_l
->ULI_Cont
->Kidneys_2
->Testes
->0varies
->UB_Cont
->Blood
->SI_Cont
->Blood
->Blood
->Blood
l->Blood
->C_Bone-S_l
->C_Bone-V
->C_Bone-S_l
->Blood
->R_Marrow
->T_Bone-V
->R_Marrow
>UB_Cont
>Blood
>Blood
>Blood
3300E+00
0000E+01
6700E+00
6600E-01
1500E+00
1500E+00
6600E-01
0300E-01
1600E-01
7000E-04
8000E-04
6300E+00
8500E-03
9000E-05
3860E+00
3900E-02
9000E-05
6000E-03
2200E-03
2200E-03
2200E-03
6000E-03
2200E-03
2200E-03
2200E-03
9000E-02
3900E-03
9000E-04
9000E-04
3300E+00
0000E+01
6700E+00
6600E-01
1500E+00
1500E+00
6600E-01
0300E-01
1600E-01
0000E-04
7000E-04
6300E+00
8500E-03
9000E-05
3860E+00
3900E-02
9000E-05
6000E-03
8800E-03
8800E-03
8800E-03
6000E-03
8800E-03
8800E-03
8800E-03
9000E-02
3900E-03
9000E-04
9000E-04
9800E+00
0000E+01
6700E+00
6600E-01
8200E+00
8200E+00
6600E-01
0300E-01
1600E-01
9000E-04
3000E-04
6300E+00
8500E-03
9000E-05
3860E+00
3900E-02
9000E-05
6000E-03
5300E-03
5300E-03
5300E-03
6000E-03
8100E-03
8100E-03
8100E-03
9000E-02
3900E-03
9000E-04
9000E-04
9800E+00
0000E+01
6700E+00
6600E-01
8200E+00
8200E+00
6600E-01
0300E-01
1600E-01
3000E-04
6000E-03
6300E+00
8500E-03
9000E-05
3860E+00
3900E-02
9000E-05
6000E-03
0400E-04
0400E-04
0400E-04
6000E-03
3200E-03
3200E-03
3200E-03
9000E-02
3900E-03
9000E-04
9000E-04
9800E+00
0000E+01
6700E+00
6600E-01
8200E+00
8200E+00
6600E-01
0300E-01
1600E-01
5000E-03
8000E-03
6300E+00
8500E-03
9000E-05
3860E+00
3900E-02
9000E-05
6000E-03
2100E-04
2100E-04
2100E-04
6000E-03
5900E-04
5900E-04
5900E-04
9000E-02
3900E-03
9000E-04
9000E-04
1.1600E+01
1.0000E+01
1.6700E+00
4.6600E-01
3.4900E+00
3.4900E+00
4.6600E-01
3.0300E-01
1.1600E-01
8.2000E-03
2.6000E-03
1.6300E+00
1.8500E-03
4.9000E-05
1.3860E+00
1.3900E-02
1.9000E-05
7.6000E-03
8.2100E-05
4.1100E-05
8.2100E-05
7.6000E-03
4.9300E-04
2.4700E-04
4.9300E-04
9.9000E-02
1.3900E-03
1.9000E-04
1.9000E-04
57
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9.0 HOW DCAL IMPLEMENTS DIFFERENT OPTIONS
CONCERNING DECAY CHAIN MEMBERS
In Chapter 5 we described different options available in the DCAL system for treating the biokinetics of decay
chain members produced in vivo. The present chapter provides some background information that may be
useful in deciding on an appropriate option for a given case and describes how the different options are
implemented in DCAL.
9.1 ASSUMPTIONS USED IN ICRP DOCUMENTS
Estimates of accumulated dose to organs following intake of a radionuclide may depend strongly on
assumptions concerning the retention of radioactive chain members produced inside the body (Leggett, Dunning
and Eckerman 1984). However, a paucity of experimental data on many important chains of radionuclides and
the desire to simplify biokinetic models and dosimetric calculations have led to the use of broad, simplistic
assumptions concerning ingrowing chain members.
In ICRP Publication 2 (1959), a radionuclide born in an organ was assigned its own characteristic biokinetic
model, meaning the biokinetic model derived for that element assuming its direct deposition into the organ from
blood. A radical departure from that approach was made in ICRP Publication 30 (1979), where decay chain
members produced in the body were assigned the biokinetic model of the parent (i.e., the radionuclide taken into
the body), with exceptions made for radioiodine produced by decay of radiotellurium and for noble gases
appearing in certain decay chains. Iodine as a daughter of tellurium was assumed to be translocated
instantaneously to the transfer compartment in inorganic form and then to follow the same kinetics as iodine
introduced into blood as a parent radionuclide. The assumption for noble gases varied with radiological half-
time and site of production in the body. For example, it was assumed that: 222Rn (Ti/2 = 3.8 d) produced from
226Ra in soft tissues escapes from the body before decay; 70% of 222Rn produced in bone escapes from the body
220 224
and the remaining 30% decays at the site of production; Rn (Ti/2 = 56 s) produced from Ra decays at the
site of production, either in soft tissues or bone; 20% of 83mKr (Ti/2 = 1.83 h) produced from 83Rb decays at the
site of production and the remaining 80% escapes from the body; and 79Kr (T, 2 = 35 h) produced from 79Rb
escapes from the body.
Current evidence suggests that the biokinetics of decay chain members may often be better described by some
combination of the assumptions made in ICRP Publications 2 and 30 (Leggett, Dunning, and Eckerman 1984;
ICRP 1993, 1995a, 1995b). That is, experimental data on laboratory animals together with limited postmortem
data on human subjects suggest that radionuclides born in soft tissues and on bone surfaces tend to relocate as if
injected directly into blood, while radionuclides born in bone volume are more limited in their ability to migrate
from the parent radionuclide (Leggett, Dunning, and Eckerman 1984). With regard to inhaled material
deposited in the lung, a reasonable default assumption may be that a radionuclide born in the respiratory tract
remains with the parent if originating in an undissolved particle but otherwise translocates according to its own
characteristic parameter values (i.e., values derived for that element assuming its direct deposition into the
respiratory tract). There is little information on the behavior of decay chain members produced in the
gastrointestinal tract, but the rate of translocation through different segments of the tract should be relatively
independent of the radionuclide. Also, in view of the tightly controlled and highly selective nature of
absorption of material through the gastrointestinal tract wall, it seems reasonable to assume that the absorption
fraction for decay chain members produced in the gastrointestinal tract contents is independent of absorption
properties of the parent radionuclide.
Some progress toward a more realistic treatment of decay chain members was achieved in ICRP Publication 67
(1993) and Publication 69(1995a). In those documents, systemic biokinetic models for radioactive progeny of
58
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isotopes of Pb, Ra, Th, or U were based on the following general principles of "independent kinetics" (i.e.,
kinetics different from that of the parent): (1) a radionuclide born in soft tissues or on bone surfaces tends to
redistribute in a manner consistent with its own characteristic biokinetic model; (2) a radionuclide born in bone
volume is more limited in its ability to relocate. Implementation of these assumptions was facilitated by the
application of biologically realistic model structures. In particular, the model structures include return of
material from organs to blood, which allows explicit depiction of migration of ingrowing activity from organs to
blood and subsequent redistribution among organs in a pattern specified by chain-member-specific models. By
contrast, all of the systemic biokinetic models of ICRP Publication 30 (1979) except the iodine model and many
of the models in the ICRP'sseries of publications on doses to members of the public (ICRP 1989,1993,1995a,
1995b, 1996) depict a physically unrealistic one-directional flow of material from organs to excreta. Such a
modeling approach precludes any physically meaningful or simple method for redistributing ingrowing activity
among systemic organs.
In the ICRP's series of documents on doses to members of the public (ICRP 1989, 1993,1995a, 1995b, 1996),
fractional absorption from the gastrointestinal tract was assumed to be element-specific for Pb, Ra, Th, or U
chains (ICRP 1993,1995a); that is, a chain member produced in vivo was assigned its element-specific f value.
For inhaled material deposited in the respiratory tract, absorption parameters of the parent generally were
applied to all members of the decay chain (ICRP 1995b). Exceptions were made for noble gases; for example,
222Rn formed in the respiratory tract was assumed to escape from the body at a rate of 100 d"1, and radioisotopes
of xenon formed in the respiratory tract from the decay of iodine were assumed to escape from the body without
decay.
9.2 TECHNICAL OR CONCEPTUAL PROBLEMS THAT MAY ARISE FROM THE
ASSUMPTION OF INDEPENDENT KINETICS OF DECAY CHAIN MEMBERS
In general, application of the principle of independent kinetics of chain members is not simply a matter of
concatenating the different biokinetic models for different chain members. Technical or conceptual problems
often arise from structural inconsistencies among models for different chain members or from a lack of
biological realism in the models. These problems may be divided into two main categories:
Category 1 problems: Structural differences in biokinetic models for different chain members that lead to an
incomplete set of conditions describing the biokinetics ofsome members. If the biokinetic models for different
chain members address different regions of the body or comprise different compartments, the situation may
arise that a decay chain member B is produced in a compartment included in the biokinetic model of a preceding
chain member but not included in the biokinetic model for B. When this happens, the rate of removal of B from
that compartment and the destination of the removed activity must be defined before the model can be solved.
Category 2 problems: Differences in the meaning of the "Other" region for different decay chain members.
Even if the biokinetic files contain sufficient information to provide a unique solution of the concatenated
models for all chain members, ambiguities may remain concerning the anatomical location of nuclear
transformations occurring in the regions of the different models referred to as "Other" or "RestofBody (ROB)".
These ambiguities may arise when the ROB compartments have different meanings for different chain
members, i.e., when the models for different decay chain members include different explicitly identified
systemic source organs. Either or both of the following situations may occur:
(a) Chain member A decays to chain member B and the biokinetic model for B contains an explicitly
identified source region S that is included implicitly in A's ROB. A portion of the decays of A in A's
ROB theoretically occur in S, but solution of the biokinetic models using the pre-defined kinetic files
(DEF files) will not reflect this.
(b) Chain member A decays to chain member B and the biokinetic model for A contains an explicitly
identified source region S that is included implicitly in B's ROB. Although the pre-defined kinetic files
59
-------
account for ingrowth of B in S (after correction of Category 1 problems, if required), they do not
account for a portion of activity of B in B's ROB that theoretically belongs to S.
Although the two types of Category 2 problems are described in terms of adjacent chain members A and B,
analogous problems for radionuclide pairs (A, B) may occur in the more general situation in which A eventually
gives rise to B through a series of decays.
Ideally, both Category I and Category II problems may be avoided by applying a common model structure to
the entire chain and providing a complete set of transfer rates for all decay chain members with respect to all
compartments in a common model. In practice, the user may not be in a position to make the modifications of
the characteristic models of different chain members required to produce such a uniform and detailed set of
transfer rates. For this reason, DCAL was designed to identify such problems, prompt the user to decide how to
resolve Category 1 problems, and provide a computer-generated resolution to Category II problems. DCAL
scans the DEF files for the different chain members for missing transfers and prompts the user to supply a
minimal amount of missing information (transfer rates) necessary to allow ACTACAL to produce a unique set
of solutions concerning the distribution of each decay chain member with respect to compartments of that chain
member's biokinetic model. Then, for dosimetric purposes only, DCAL reapportions the calculated ROB
activity of individual chain members according to a consistent scheme that provides a practical resolution to
problems 2a and 2b. The specific procedures followed in DCAL are described in the following section in
connection with DCAL's implementation of the option of using pre-defined kinetic files for each chain member.
9.3 HOW DIFFERENT OPTIONS CONCERNING DECAY CHAIN MEMBERS ARE
IMPLEMENTED IN DCAL
Recall that ACTACAL provides the following options for treating decay chain members:
1. Independent kinetics; user-predefined files.
2. Shared kinetics; ICRP-30 approach.
3. Member-by-member default options:
a. No biological translocation.
b. Prompt removal from the body.
c. Assign kinetics of first member.
9.3.1 Implementation of Option 1: Independent Kinetics: User-Predefined Files
The option of pre-defined kinetic files for each chain member can be applied to any type of assumption
concerning the behavior of decay chain members, provided the assumption is compatible with the structures of
the models being applied. However, this option is intended primarily for application of the principle of
independent kinetics of decay chain members, while Options 2 and 3 are provided for ease of application of
simplistic assumptions concerning the biokinetics of decay chain members. Use of Option 1 to implement the
simplistic assumptions covered by Options 2 and 3 requires repetitive assignment of transfer rates, a task that
can be performed by the computer.
As indicated in the preceding section with regard to the principle of independent kinetics of decay chain
members, application of Option 1 is not simply a matter of using separate DEF files for different chain
members. Before beginning an application that will involve Option 1, you should examine the DEF files for the
types of problems described above and, as far as practical, modify the files for consistency as well as for
purposes of achieving the intended behavior of ingrowing decay chain members. If you apply the pre-defined
kinetic files describing the models of Federal Guidance Report 13 (EPA 1999) (in folder \DAT\BIO\FGR13) or
the models of ICRP Publication 68 (1994b) (in folder \DAT\BIO\I68) and follow the assumptions concerning
decay chain members in the corresponding documents, then no modifications of DEF files are needed.
When Option 1 is selected, the following steps are followed in ACTACAL:
60
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Step 1. The biokinetic models (DEF files) of all chain members are scanned to establish a
common set of source regions for the entire chain. This set of source regions consists of
explicitly identified source regions appearing in a model of any decay chain member, plus a
common source region "Other" consisting of tissues remaining after subtraction of all the
explicitly identified source regions. Recall that a region is considered a source region for a
given radionuclide provided it receives that radionuclide from one or more sources other than
by ingrowth through radioactive decay. An explicitly identified source region is a region with
an explicitly identified anatomical name.
In the following, we use "ROB" when referring to the "Other" region in the biokinetic model for a
specific chain member and reserve the term "Other" for the source organ common to the entire chain.
Step 2. The mass of ROB for each chain member is computed.
Step 3. The DEF files for different chain members are scanned to determine whether Category
1 problems exist (see the preceding section). If such problems are found, the user is prompted
to supply missing transfers (see Section 5). When a minimal set of transfers is available to
describe the kinetics of all ingrowing activity in all regions, the time-dependent activities in the
compartments of the biokinetic model for each chain member are computed using the
biokinetics described by the pre-defined kinetic files (DEF files).
Step 4. The activities in the compartments are assigned to source regions based on the naming
convention of the DEF files (see Section 3). The activity associated with a source region is the
sum of the activities in the compartments of the region.
Step 5. The following additional adjustments are made, if applicable:
(a) For a source region S of a member's (B's) biokinetic model that is not explicitly
identified in the model of any preceding chain member, a fraction of B's ROB activity
is added to its computed activity in S. Also, for each member C following B in the
chain, a fraction of C's ROB activity is added to C's computed activity in S. The
fraction added in each case is the mass fraction of S relative to the mass of ROB in the
parent's biokinetic model. The member's ROB activity is decreased by the activity
assigned to S.
(b) For a source region S of the chain that is not an explicit source region in a chain
member's (M's) biokinetics, a fraction of M's ROB activity is added to S. The fraction
is the mass fraction of S relative to the mass of M's ROB. The activity of M's ROB is
decreased by the activity assigned to S. If Step 5a also applies to M because S is an
explicitly identified source organ of a preceding chain member B but is not an
explicitly identified source organ of the first member of the chain, then Step 5a is
carried out and Step 5b is omitted. Note that the adjustment of the activity of M in S
that would result from Step 5a usually is not precisely the same as the adjustment that
would result from Step 5b, because the two adjustments depend on the masses of two
different ROBs. In most cases, however, these two masses differ by at most a few
percent, and making both adjustments would usually result in relocation of roughly
two times too much activity of M from ROB to S.
Step 6. If item 5a or 5b is applicable to some chain member, that member's activity in the
common source organ "Other" is set equal to the adjusted activity in ROB.
61
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It is emphasized that the above reapportionments of activity are made for dosimetric purposes only and are
made external to ACTACAL solutions of the time-dependent distribution of activity in compartments.
Adjustments made for a given time do not affect ACTACAL's calculations for a later time. As indicated in Step
3, the activities in the compartments of the biokinetics for each chain member are computed solely on the basis
of the pre-defined kinetic files.
9.3.2 Implementation of Option 2: The "ICRP-30" Approach
This refers to the general principle as well as the exceptional cases first applied in ICRP Publication 30 (1979)
and, with some exceptions, carried over to ICRP Publication 68 (1994b). That is, decay chain members
produced in the body generally are assigned the biokinetic model of the parent, except that (a) radioiodine
produced by decay of radiotellurium is assigned the characteristic biokinetic model for iodine, and (b) noble
gases in certain decay chains are assigned special models (assumptions) that vary with the radiological half-time
of the noble gas and the site of production in the body.
When this option is selected, DCAL assigns to each non-exceptional decay chain member the same
compartments and transfer rates that appear in the DEF file for the parent. The models and/or assumptions for
the exceptional decay chain members are "hard-wired" into the ACTACAL subroutine, i.e., are described within
the computer code rather than by input data.
Option 2 may be applied whether or not the biokinetic models of ICRP Publication 30 are used, but the models
for the exceptional decay chain members cannot be changed. Application of the general principles of ICRP
Publication 30 but with different assumptions for these exceptional cases, or with additional exceptions to the
general principle, would require selection of the first option (pre-defined kinetic models for all chain members)
after the appropriate biokinetic (DEF) files have been created and inserted into the DCAL library.
9.3.3 Implementation of Option 3: Member-bv-Member Default Options
These options are applied individually to decay chain members. For example, one could assign Assumption 3a
to the second decay chain member, Assumption 3c to the third, Assumption 3a to the fourth, Assumption 3b to
the fifth, and so forth.
Assumption 3a (no biological translocation) is implemented in DCAL as follows: The same paths of movement
described in the biokinetic (DEF) file for the parent are assigned to the decay chain member (B). Then the
transfer rate of B along each path is set at 10"10 d"1.
Assumption 3b (prompt removal from the body) is implemented as follows: First, the same paths of movement
and transfer rates described in the biokinetic (DEF) file for the parent are assigned to the decay chain member
(B). Second, for each path of movement X to Y depicted in the model, an additional path of movement from X
to excreta is added. Third, the transfer rate of B along each additional path is set at 1000 d"1, corresponding to a
biological half-time of about 1 min.
Assumption 3c (assign kinetics of first member) is implemented in the obvious way, i.e., the paths of movement
and transfer rates in the biokinetic file for the parent are assigned without change to the decay chain member.
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10. HOW DCAL ESTIMATES THE RISK OF RADIOGENIC CANCERS
10.1 GENERAL CONSIDERATIONS
The risk calculations performed by DCAL are for attributable risk. Attributable risk is the likelihood, according
to a given risk model, of death from cancer or development of cancer due to a radiation exposure.
Calculations of attributable risk are based on risk projection models for specific cancer sites. The age- and
gender-specific radiation risk models used in DCAL are taken from an EPA report (EPA 1994) that provides a
methodology for calculation of radiogenic cancer risks based on a critical review of data on the Japanese atomic
bomb survivors and other study groups. Some parameter values in those models have been modified for use in
DCAL to reflect updated vital statistics for the U. S. and to achieve greater consistency in the assumptions made
for different age groups and genders. The following age-at-exposure groups are considered in the models: 0-9,
10-19, 20-29, 30-39, and 40+ y.
In estimating the likelihood of a radiogenic cancer, it is considered that an exposed person may die from a
competing cause before a radiogenic cancer could develop. For some of the cancer sites considered in DCAL,
the risk model is based on the assumption that the likelihood of a radiogenic cancer depends on the baseline
cancer mortality rate in the population. The gender-specific survival data and mortality data for specific cancers
used by DCAL are based on vital statistics for the United States.
Age-specific risk coefficients generally are average values for fairly broad age intervals and are discontinuous at
the endpoints of these intervals. Also, vital statistics for the U.S. are discrete data, typically tabulated atone or
five year intervals. For use in DCAL, risk coefficients and vital statistics have been transformed into
continuous functions by fitting a cubic spline to the discrete data. DCAL calculates interpolated values,
derivatives, and integrals directly from the spline coefficients (de Boor 1978, Fritsch and Carlson 1980; Fritsch
and Butland 1982).
10.2 EXPOSURE SCENARIOS
Estimates of attributable risk calculated by DCAL for internally deposited activity are based on a lifetime intake
of the parent radionuclide of 1 Bq. The intake rate is assumed to be proportional to the usage of the
environmental medium containing the radionuclide. Intakes may be by any one of the three intake modes for
which DCAL can generate absorbed dose rate files, i.e., inhalation, ingestion, or injection.
A dose rate file generated by DCAL for internally deposited activity is based on acute intake of a radionuclide
at a specified age. Age-specific dose rates to organs during chronic intakes can be estimated from the files
generated for acute intakes by considering a chronic intake as a large number of small, acute intakes spaced over
the intake interval.
The default ages at acute intake considered by DCAL are infant (100 d), 1 y, 5 y, 10 y, 15 y, and adult (20 or
25 y, depending on the biokinetic model). Dose rates following intake at some age other than a default age are
estimated by linearly interpolating data for the default ages. Dose rates for acute intake as a young adult are
applied to intake at any adult age.
For each of the internal exposure modes, the risk coefficient for a radionuclide includes the contribution to dose
from production of decay chain members in the body after intake of the parent radionuclide, regardless of the
half-lives of the decay chain members. For both internal and external exposure, a risk coefficient for a given
radionuclide is based on the assumption that this is the only radionuclide present in the environmental medium.
63
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That is, doses due to decay chain members produced in the environment prior to intake of, or external exposure
to, the radionuclide are not considered. However, a separate risk coefficient is provided for each decay chain
member of potential dosimetric significance. This allows the user to assess the risks from radionuclides
produced in the environment by radioactive decay of parent radionuclides.
10.3 RISK MODELS USED IN DCAL
One of two basic types of radiogenic cancer risk projection model is used for a given cancer site: an absolute
risk model or a relative risk model. An absolute risk model is based on the assumption that the age-specific
excess force of mortality or morbidity (that is, the mortality or morbidity rate for a given cancer type) due to a
radiation dose is independent of cancer mortality or morbidity rates in the population. A relative risk model is
based on the assumption that the age-specific excess force of mortality or morbidity due to a radiation dose is
the product of an exposure-age-specific relative risk coefficient and baseline cancer mortality or morbidity rate.
The risk models used in DCAL for bone, skin, and thyroid cancer are based on an absolute risk hypothesis, and
risk models for other sites are based on a relative risk hypothesis.
In an absolute risk model, the absolute risk at age x due to a unit absorbed dose received at an earlier age y is
calculated as the product A (y) B{t) where A is an age- and gender-specific "risk model coefficient", B is a time-
since exposure step function that defines the plateau period (the time period during which the risk is expressed),
and t = x- y. The value of B(t) is 1 for times t within the plateau period and otherwise is 0. In a relative risk
model, the risk is calculated as the product C(x.y) D(y) E(t,y), where C(x.y) represents the baseline force of
cancer mortality at age x due to a unit absorbed dose received at age y
-------
Table 10.1. Mortality risk model coefficients for cancers other than leukemia,
based on the EPA radiation risk methodology (EPA 1994)
Risk Age group
model
Cancer type type3 0-9 y 10-19 y 20-29 y 30-39 y 40+y
Male:
Esophagus
R
0.2877
0.2877
0.2877
0.2877
0.2877
Stomach
R
1.223
1.972
2.044
0.3024
0.2745
Colon
R
2.290
2.290
0.2787
0.4395
0.08881
Liver
R
0.9877
0.9877
0.9877
0.9877
0.9877
Lung
R
0.4480
0.4480
0.0435
0.1315
0.1680
Bone
A
0.09387
0.09387
0.09387
0.09387
0.09387
Skin
A
0.06597
0.06597
0.06597
0.06597
0.06597
Breast
R
0.0
0.0
0.0
0.0
0.0
Ovary
R
0.0
0.0
0.0
0.0
0.0
Bladder
R
1.037
1.037
1.037
1.037
1.037
Kidney
R
0.2938
0.2938
0.2938
0.2938
0.2938
Thyroid
A
0.1667
0.1667
0.08333
0.08333
0.08333
Residual
R
0.5349
0.5349
0.6093
0.2114
0.04071
-emale:
Esophagus
R
1.805
1.805
1.805
1.805
1.805
Stomach
R
3.581
4.585
4.552
0.6309
0.5424
Colon
R
3.265
3.265
0.6183
0.8921
0.1921
Liver
R
0.9877
0.9877
0.9877
0.9877
0.9877
Lung
R
1.359
1.359
0.1620
0.4396
0.6047
Bone
A
0.09387
0.09387
0.09387
0.09387
0.09387
Skin
A
0.06597
0.06597
0.06597
0.06597
0.06597
Breast
R
0.7000
0.7000
0.3000
0.3000
0.1000
Ovary
R
0.7185
0.7185
0.7185
0.7185
0.7185
Bladder
R
1.049
1.049
1.049
1.049
1.049
Kidney
R
0.2938
0.2938
0.2938
0.2938
0.2938
Thyroid
A
0.3333
0.3333
0.1667
0.1667
0.1667
Residual
R
1.122
1.122
0.8854
0.3592
0.1175
aA indicates that an absolute risk model is used (coefficient units, 10"4 Gy"1 y"1), and R indicates that a relative
risk model is used (Gy-1).
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Table 10.2. Mortality risk model coefficients (Gy1) for leukemia, based on the EPA
radiation risk methodology (EPA 1994)a
Age group
Gender 0-9 y 10-19 y 20-29 y 30-39 y 40+ y
Male 982.3 311.3 416.6 264.4 143.6
Female: 1176 284.9 370.0 178.8 157.1
aA relative risk model is used (coefficient units, Gy"1). Risk model coefficients for leukemia are
not directly comparable to those for other types of cancer (Table 10.1) due to differences in the
scales of the time-since-exposure response functions for leukemia and other cancers.
Table 10.3. Lethality data for cancers by site in adults
Cancer site
Lethality fraction k
Esophagus
0.95
Stomach
0.90
Colon
0.55
Liver
0.95
Lung
0.95
Bone
0.70
Skinb
0.002
Breast
0.50
Ovary
0.70
Bladder
0.50
Kidney
0.65
Thyroid
0.10
Leukemia (acute)
0.99
Residual
0.71
10.4 Continuity Considerations
While the integration of a smoothly varying function using a spline is straightforward, the radiogenic cancer
models are inherently discontinuous. For example, the time since exposure function for most solid cancers
typically has a value of zero for times since exposure that are less than the 10 y minimal latency and a value of
one for times equal to or greater than the minimal latency. Suppose that the function to be integrated (the
integrand) is evaluated at one year increments. For the models used in DCAL, the function will change abruptly
from a value of zero for times since exposure less than 10 y to a generally smoothly varying function of time for
times equal to or greater than 10 years. However, fitting a spline to the integrand provides a continuous
transition from the value at 9 y to the value at 10 y. If the integral is evaluated on the basis of these spline
coefficients, it will include an unintended contribution from this interval.
One way to solve the problem is to integrate functions in piecewise continuous intervals. This method is exact
and would work well for the simple example considered above. In general, however, the value of the integrand
at each discontinuity depends on the interval of integration; the method becomes unwieldy for situations with
many discontinuities. An alternative method for situations where the function is reasonably smooth on either
side of a discontinuity is to replace the value of the function at the discontinuity with the average of the values
immediately above and below it. For the case above, the value of the time since exposure response function at
10 y is changed from lto(0 + l)/2 = 0.5. The reduced excess in the integral between 9 and 10 y is then
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compensated for by a comparable reduction in the 10 to 11 year interval. This method was used to smooth the
risks and lifetime losses represented in the risk models used in DCAL.
10.5 Cancer Type and Dose Location Associations
The dose locations associated with each cancer type are shown in Table 10.4. When more than one dose
location is shown in the table, risks are calculated for a weighted mean of the doses at these locations using the
weights shown in the table. The residual cancer category represents a composite of primary and secondary
cancers that are not otherwise considered in the model. The dose location associated with these cancers, the
pancreas, was chosen to be generally representative of soft tissues; the pancreas is not considered the origin of
all these neoplasms.
Table 10.4. Dose regions associated with cancer types
Cancer type
Dose region
Weighting factor
Esophagus
Esophagus3
1.0
Stomach
Stomach Wall
1.0
Colon
Upper Large Intestine Wall
Lower Large Intestine Wall
0.568
0.432
Liver
Liver
1.0
Lung
Bronchial Region - Basal Cells
Bronchial Region - Secretory Cells
Bronchiolar Region - Secretory Cells
Alveolar-Interstitial Region
0.1667
0.1667
0.3333
0.3333
Bone
Bone Surface
1.0
Skin
Skin
1.0
Breast
Breasts
1.0
Ovary
Ovaries
1.0
Bladder
Urinary Bladder Wall
1.0
Kidney
Kidney
1.0
Thyroid
Thyroid
1.0
Leukemia
Red Marrow
1.0
Residual
Muscle
Pancreas
Adrenals
0.3334
0.3333
0.3333
"For intakes of radionuclides, the estimated dose to the thymus is applied to the esophagus, which
is not represented explicitly in the mathematical phantoms used for internal dosimetric calculations.
The esophagus is represented explicitly in the phantom used for external dose calculations (EPA
1993).
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11. EXTERNAL DOSE COMPUTATIONAL MODULE
In this section we describe the external computational module EXTDOSE included within DCAL. The DCAL
system was developed largely to address the doses and risks resulting from the intake of radionuclides.
However, the EXTDOSE module, initially developed during the preparation of Federal Guidance Report 12
(EPA 1993), has been integrated into DCAL.
11.1 FGR-12 CALCULATIONAL METHODS
Photons and electrons are the most important radiations emitted by radionuclides distributed in the environment
that can penetrate the body from outside to deposit ionizing energy within its radiosensitive tissues. This
section briefly discusses the methods used to calculate the dose coefficients for external exposure to photons
and electrons for submersion in contaminated air, immersion in contaminated water, and exposure to
contaminated ground surfaces and volumes.
Some radionuclides produce bremsstrahlung that can contribute to the external dose. In Federal Guidance
Report 12, the contribution from bremsstrahlung was included in the dose calculations. The version of
EXTDOSE incorporated into DCAL address bremsstrahlung however it differs from the earlier version in that
the bremsstrahlung contribution is computed directly rather than read from apre-calculated data file. This result
in minor numerical differences in external coefficients derived using DCAL and those tabulated in FGR 12 for
pure beta emitters; e.g., Sr-90. In addition, the radiations associated with spontaneous fission are taken into
account in the DCAL version which results in external dose coefficients derived using DCAL for such emitters
(e.g., Cf-252) that differ from those tabulated in Federal Guidance Report 12.
11.2 ORGAN DOSES FROM MONOENERGETIC ENVIRONMENTAL PHOTON SOURCES
The calculation of organ doses from irradiation of the body by photon emitters distributed in the environment
requires the solution of a complex radiation transport problem. It is impractical to solve this problem for the
precise spectrum of photons emitted by each radionuclide. Therefore, in Federal Guidance Report 12, organ
doses were computed for monoenergetic photon sources at twelve energies between 0.01 and 5.0 MeV. These
results were then used in Federal Guidance Report 12 and here by EXTDOSE to derive radionuclide-specific
dose coefficients. EXTDOSE considers exposure to radionuclides distributed:
• in the air surrounding an individual (submersion)
• in the water which the individual is immersed (immersion)
• on the surface of the ground
• in the top 1-, 5-, or 15 cm layer of soil
• uniformly within the soil depth
Federal Guidance Report 12 describes in detail the computations of the organ dose for a monoenergetic photon
emitter distributed as above. The organ doses for such an emitter are contained in Tables II.4 - II.6, and Tables
II. 12 - II. 15 of Federal Guidance Report 12 and these data are included in the folder \DCAL\DAT\EXT.
11.3 SKIN DOSES FROM MONOENERGETIC ENVIRONMENTAL ELECTRON SOURCES
The contribution of electrons to dose to organs and tissues of the body other than skin need not be considered,
due to the short range in tissue of electrons emitted by radionuclides. The DOSFACTER code developed by
Kocher (DOE 1988) was used to calculate skin dose coefficients for a series of monoenergetic electron
emissions, which were convoluted to the spectra of the various radionuclides, using the energy and intensity of
beta and electron emissions of radionuclides tabulated in ICRP Publication 38 (ICRP 1983; Eckerman et al.
1993). In Federal Guidance Report 12, skin doses forthe monoenergetic emissions were presented in a series
68
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of graphs (Figs II.24-II.26) and these data are contained in data files in \DCAL\DAT\EXT. For a discussion of
the computational details see Kocher (DOE 1988) or Federal Guidance Report 12.
11.4 DOSE COEFFICIENT FORMULATION FOR RADIONUCLIDES
The energies and intensities of the radiations emitted in spontaneous nuclear transformations of radionuclides
are contained in the nuclear decay data files in the folder \DCAL\DAT\NUC. These files have been described
by Eckerman et al. (1993), provide a complete tabulation of the energies (average or unique) and intensities of
the emitted radiations including the beta spectra.
Only photons and electrons (including bremsstrahlung) emitted by the radionuclides are sufficiently penetrating
to contribute to the dose to tissues and organs of the body. The energy spectra of emitted radiations are either
(1) discrete, as in the case of gamma emissions, or (2) continuous, as in the case of bremsstrahlung and beta
particles. The beta spectral file is used here to evaluate the contribution of the beta particles to the skin dose.
The dose coefficient hj for tissue T and exposure mode S can be expressed as
where y/I'-j is the yield of discrete radiations of type j and energy Eh and y/E) denotes the yield of continuous
radiations per nuclear transformation with energy between E and E + dE. The other summation is over all
electron and photon radiations while the two terms within the bracket address the contributions of the discrete
and the continuous emissions. The contribution of the radiations to the dose in tissue or organ T is defined by
discrete emissions, a value appropriate to the energy of the discrete radiation being evaluated is obtained by
interpolation. For photons, these data are tabulated for 25 target tissues of the body at each of 12 monoenergetic
photon energies and for electrons the values are tabulated only for the skin.
11.5 EXTDOSE CALCULATIONS
To initiate calculations of the external dose coefficients, select EXTDOSE from the DCAL main menu. Note
that the results of the calculations will be contained in the work folder indicated at the bottom of the main menu,
i.e., labeled by . Following the credit display, the following prompt appears
I so (l')ile or (i)nput nuclides (|l'|/i)?
If we elect to input the radionuclides of interest (response /'), this results in the following prompts
Input nuclides of interest, e.g., Ii:i-137m
'KikI' or hhink response exits input routine.
As the nuclides are entered, they are written to a scratch file to be processed after the input is complete.
If the user had created a file, using an ASCII editor (or Windows notepad), in the work folder, then electing that
option would result in a request to identify the file name
Input Ilk' name -
(11.1)
J- e. y
the quantity ffT (E) which is tabulated as a function of energy for each exposure mode. In the case of the
Nuclide ->?
TTT
-------
The work folder \wrk\work2 contains the example file EXTLIST.INP for illustrative purposes. Entering
EXTLIST will result in the following prompt (this prompt also appears after entering the nuclides of
interest).
In indiaUc llic cn\ iron menial mcdm w i ill in w Inch llic radionuclides niv disln lulled IT "soil" is idcnlilicd. llicn
Source moiliii: (:i)ir. (\\):itcr, or (s)oil (|:i|/\\/s)?
additional information on the distribution is requested
Distribution: (s)urf;uc or (\ Milium* (|s|/\)?
Selecting a volume distribution results in an additional prompt concerning the depth to which the radionuclides
are distributed
(I) cm, (5) cm, (15) cm, or (i)nrinito thickness? ->
The calculations then proceed based on the above information. The output file name is controlled by the
EXTDOSE.INI file. The entries in that file of interest are
'dfful.sub' ,
'tabsubm.dat'
0
table:
submersion
'dfful.imm' ,
'tabwater.dat'
0
table:
water immersion
'dffulsur.grd',
'tabsurf.dat'
0
table:
ground surface source
'dffull.grd' ,
'tablcm.dat'
0
table:
1 cm slab soil source
'dfful5.grd' ,
'tab5cm.dat'
0
table:
5 cm slab soil source
'dffull5.grd' ,
'tabl5cm.dat'
0
table:
15 cm slab soil source
'dffulinf.grd',
'tabinfin.dat'
0
table:
infinite slab soil source
Recall that the second field is the name assigned to the actual files and the text at the extreme right serves as a
reminder of the file content. Thus, if we elect to evaluate the radionuclides distributed in air, the results of the
calculations will be contained in the file TABSUM.DAT in the work folder. In addition, EXTDOSE, like the
other computational modules, will check for the INI file in the work folder, thus enabling the user to make use
of a INI specific to the particular work folder.
70
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The screen output when the example input file is run is shown below.
EXTDOSE: External Dose Calculation
Ver. 5.0 (May 20, 2001)
Authors: K.F. Eckerman & J.C. Ryman
Oak Ridge National Laboratory
Oak Ridge, TN 37831-6480
Use (f)ile or (i)nput nuclides <[f]/i)? f
Input file name (ext INP assumed)-> extexamp
Source media: (a)ir, (w)ater, or (s)oil ([a]/w/s)? a
Nuclide
Tl/2
Dec Mode
Photon
Elect
B
H-3
12.35y
B-
0
0
1
Co-60
5.271y
B-
6
40
3
1-131
8 . 04d
B-
25
129
6
Cs-137
30. Oy
B-
0
0
2
Ba-137m
2.552m
IT
3
27
0
Th-232 1
.405E10y
A
23
32
0
Elapsed
time (100
s) =
5
Press any
key to continue .
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12. DCAL'S UTILITY ROUTINES
DCAL includes a number of utility routines which provide additional capabilities and access to the
computational results. The utilities can be invoked either via the menu bar on DCAL's main men u or from the
function keys while DCAL's main menu is displayed. In this chapter we briefly discuss these utilities.
12. 1. UTILITIES INVOKED FROM DCAL MAIN MENU
12.1.1 View Work Files - List
This menu item enables the user to view the output files in the work folder, indicated by the key on
DCAL's main menu display, for the current or active case (the case can be determined by press ).
Selecting this menu item invokes PBVIEW32.EXE residing in the BIN folder. From PBVIEW32's menu the
file of interest can be selected for viewing on the screen. The arrow key (up and down, left and right) can be
used to examine the file. See Fig. 5.1 for an example of PBVIEW32's display.
The popular shareware DOS utility LIST3 can be used as an alternative to PBVIEW32. This DOS utility will be
used by DCAL2005.EXE ifLIST.COM is present in DCAL's BIN folder.
12.1.2 Plot Selected Data - PLOTEM
This menu item invokes the plotting facility, PLOTEM, which provides a visual inspection of the activity (ACT
and CPT files) and dose rate files (DRT and HRT files) of the current interactive case. A series of menus are
provided to select the specific data for plotting. This utility is not intended to produce publication quality plots
but rather to provide for a prompt visual inspection of the data. The export utility EXPORTM (invoked by the
key) can be used to export the data for input into a plotting program or spreadsheet program. Fig. 12.1
illustrates a plot of the 90Sr and 90Y activity in cortical bone following an ingestion intake by a worker.
PLOTEM is a 32 bit console application (executable is PLOT32.EXE) and functions in a manner typical of
Windows applications; e.g., the mouse can be used to respond to its menus. The graphics are generated using
DPlot Jr4. DPlot Jr provides a quick means to generate and display graphical output from a developer's code.
Input to DPlot Jr is accomplished through Dynamic Data Exchange (DDE), with PLOTEM as the driving
module. DPlot Jr lacks many of the editing and data input features of full-blown plotting package; e.g., as in
DPlot1, however its capability more than satisfies DCAL's needs.
When PLOTEM is invoked its initial menu lists the files; e.g., ACT, DRT, and HRT, associated with the current
cases from which data might be selected for plotting as the "Files of type" option defaults to "Current DCAL
Case." A menu of all the files in the work folder can be obtained by pulling down the "Files to type" window to
show "All files". The file of interest is then selected and from subsequent menus the data set of interest selected
for plotting; e.g., from an * .ACT file the activity in the source region "Blood" as a function of time. Multiple
data sets can be plotted by selecting the data sets from the menu and then viewing the plots setting Windows'
focus on the DPlot Jr screen (click on the screen).
PLOTEM's graphic of the Sr-90/Y-90 activity in the volume of cortical bone following an ingestion intake of
Sr-90 is shown in Fig. 12.1. Note DPlot Jr's menu bar in the figure. Under the "Options" item the "Linear/Log
Scaling" and the "Extent/Tick marks/Size... "entries can be used to change the type of x- and j-axis and their
3 The LIST utility can be downloaded from /www.buerg.com/.
4 DPlot Jr is available from HydeSoft Computing, Inc., 110 Roseland Drive, Vicksburg, MS 39180 and can be
downloaded from the website www.dplot.com/index.htm.
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numerical range. If multiple plots were requested from PLOTEM's menu they can be displayed via the
"Window" item. Additional information regarding DPlot Jr" s functions can be obtained from "Help" on the
menu bar. Plots can be saved and printed from the "File" item.
To exit PLOTEM, use the Alt-Tab key combination to display PLOTEM's menu and click on ""Cancel". You
are then asked to close the DPlot Jr window, and then click on ""Cancel ' to return to the main menu display.
The DCAL and DPlot Jr icons will be visible as you toggle the Alt-Tab key combination and then you can close
DPlot Jr by clicking on the X button in the upper right corner of the display.
~mi
~JXDT
~HD5
ojhd
~hie
S3 DPlot Jr - [ C_Bone-V]
|5[ File Edit Text Options Info View Window Help
H # % ^ 13 tk m E2 T. til I
£* bs: H:: Q «; | *?
SR-90AG_.ACT: C_Bone-V
Fig. 12.1. DCAL's PLOTEM display. DPlot Jr graphic display of the Sr-90/Y-90 activity in the
volume of cortical bone following an ingestion intake of 1 Bq by an adult.
12.1.3 Tabulate Dose Coefficients - HTAB
The utility HTAB can be used to tabulate the committed absorbed dose (EPACAL's output file *.DRT) or
equivalent dose (EPACAL's output file * HRT) dose coefficients. This utility can only be used in the interactive
mode as the $STEMNAM.DIR file, written by ACTACAL, is used to identify the current case. The current or
active case, the contents of SSTEMNAM.DIR, can be displayed by pressing . If the user elected to
compute absorbed dose then the summary table will list the low and high LET components of the absorbed
dose. For inhalation cases, the user will be query as to whether the dose coefficients for the regions of the lung
(ET1, ET2... AI) should be tabulated. The tabulation created by HTAB are saved as * HEF when * is the root
name of the active case. See Fig. 5.1 for an example of such a file.
73
-------
12.1.4 Nuclide Emissions - RADSUM
This utility summarizes the emitted radiations of the user specified radionuclide. The utility displays aperiodic
chart and using the mouse the radioelement of interest is selected (see Fig. 12.2). If data for radioisotopes of the
element are included in the nuclear decay data library a menu of available radionuclides is displayed. Clicking
on the radionuclide of interest results in a summary display of its emission (see Fig. 12.3). The half-life, specific
activity, and decay mode of the selected radionuclide are shown in the display. The emitted radiations are
summarized is six categories; alpha, gamma rays, x-rays, beta -, beta +, internal conversion electrons, and Auger
electrons. The number, frequency, total and average energy of the emissions in each category as well as the
total over the categories are displayed. If the radionuclide decays by beta decay the average energy of the beta
spectra is computed and displayed. For photon emitters the gamma constant in conventional units and SI units
is also displayed. RADSUM does not provide any information regarding the emissions accompanying
spontaneous fission. Finally, we note that users may create a shortcut to the RADSUM32.EXE to be able to
invoke this module directly from the desktop without invoking DCAL.
|^Rad5um32: Summary of Nuclide Emissions
dnlJi!
Be 4
Me 12
C a 2«i
Sc 21
Sr 38
Y 39
Ka 88
Ac 89
Legend
Alkali Metals
Alkaline Earth
Metals
Trans. Metals
| Noble Gases
Actmides
Latitliariiiles
Non Metals
Halogens
VIIIE
IIIB IVE VB VIB VIIB
IIIA IVA VA VIA VIIA
¦ VIIIA ¦
IB IIB
Ti 22
Zr 40
Hf 72
V 23
Nb 41
Ta 73
Cr 24
Mo 42
W 74
Tc 43
Re 75
Fe 26
Ru 44
Os 76
Co 27
Rh 45
Ir 77
Ni 28
Pd 46
Pt 78
Cu 29
Ag 47
Au 79
£n30
Cd 48
Hg 80
B5C6N7 08F9
Si 14 P 15 S 16 CI 17
As 33 Se 34 Br 35
A113
Ga 31
In 49
Ge 32
Sn 50
II 81 Pb82
Sb 51
Bi 83
Te 52 1 53
Po 84 At 85
He 2
Ne 10
Ar 18
Kr 36
Se 54
Rn 86
Lanthamde
Series
Actiiiiie
Series
Ce 58
Pr 59
Nd 60
Pm 61
Sm 62
Eu 63
Gd 64
lb 65
Dy 66
Ho 67
Er 68
Tm 69
Yb70
r
-i
Th 90
Pa 91
U 92
Np 9 3
Pu 94
Am 95
Cm 9t
Bk 97
Cf 98
Es 99
FmlOO
MdlOl Nol02
Lrl03
Click on an element to list its radioisotopes.
Press to exit RADSUM32.
Plutonium: Pu
Fig. 12.2. RADSUM display from which the radioisotope of interest is selected. The position of the
mouse is not evident in the figure. The information in the lower right corner is updated as the mouse
is moved over the elements. A list of the radioisotopes of the element is displayed by clicking of an
element
74
-------
Gamma rays
X-rays
Beta -
IG electrons
finger electrons
Alpha part icle s
Total Emitted Energy = 5.365E-03 MeU/nt
Average energy of beta spectrum = 5.235E-03 Mel)
Gamma Constant = 2.229E-04 R cmA2/(mCi hr)
Kerma Constant = 1.462E-21 Gy mA2/
Press any key to continue...._
Half-Life : 14.4 y
Decay Mode: A B-
Radioactive daughters & branching fractions
Am-241 1.000E+00 U-237 2.450E-05
Radiation
Frequency
£ Yi
Number
13 3.455E-06
21 7.362E-05
1 1.000E+00
65 1.783E-04
21 2.829E-04
11 2.450E-05
4.268E-07
2.119E-06
5.236E-03
4.937E-06
1.420E-06
1.199E-04
Mean Energy
E¥i*Ei/£¥i
1.235E-01
2.878E-02
5.236E-03
2.770E-02
5.018E-03
4.894E+00
SpA = 3.811E+00 TBq/g
Data file: ICRP38
Fig. 12.3. RADSUM's summary table of the emissions of Pu-241. If the selected radionuclide decays
to radioactive daughters the daughters and their branching fractions are listed in the display.
12.1.5 Decay Chain Details - CHAIN
This utility tabulates the decay chain for the specified radionuclide and tabulates the number of nuclear
transformations over a 100-y period for each chain member as well as the cumulative energies, by type of
radiation, over that period. The radionuclide of interest is selected in the manner of RADSUM (see Fig.
12.2).As an example, below is the tabulation for 9ilSr/®DY chain.
Sr-90 Decay Chain: Half-lives and Branching Fractions
Nuclide
Halflife fl Nuclide f2 Nuclide f3 Nuclide
1 Sr-90
29.12y 1.0+00-> 2 Y-90
2 Y-90
64. Oh
Sr-90: Activity, Transformations, & Cumulative Energies (MeV)
at lOOy
Nuclide
Tl/2 A(t)/Ao intA/Ao(d) Ealpha Ebeta
Egamma
1 Sr-90
29.12y 9.25216D-02 1.39249D+04 0.00E+00 2.73E+03
0 . 00E+00
2 Y-90
64. Oh 9.25448D-02 1.39246D+04 0.00E+00 1.57E+04
0 . 00E+00
The numerical values tabulated in the last three columns in CHAIN'S second table above represent the
cumulative energies emitted by alpha, beta (including discrete electrons), and photons (gamma and x-rays) for
nuclear transformations occurring over 100 years in a sample consisting initially of 1 Bq of the parent. The
third and fourth columns in the second table represent the fractional activity at 100 y and the fractional
integrated activity (d) at 100 y, respectively for each chain member. The cumulative energies indicate for each
chain member is a aid in determining whether the decay chain may be truncated without substantially affecting
dose estimates. ACTACAL makes such a decision based on a virtual lack of increase in cumulative energy
beyond some chain member; however it can be is useful to use the CHAIN utility to preview the situation.
The CHAIN utility uses information in the NDX files (for example, ICRP38.NDX) to construct the chain and
compute the cumulative energies.
The serial transformation by radioactive decay of each member of a radioactive series is described by the
75
-------
Bateman equations (EPA 1993). Assume that at time zero the activity of the parent nuclide is A" and that of all
daughters is zero. The activity at time t of a chain member i = 1, 2, ..., can be expressed as
A,(t ) ^ ex,t
I7fh]+l AjZ-
A° ¦>=' n( - /- >
tVi (12.1)
" fa, a2 a3 ...an , if n>\
na'=|l,ifn=0
Where /. j+l denotes denotes the fraction of the nuclear transformations of chain member j forming member
7+7,and /,,¦ is the decay constant for nuclide / (/, 0.6931... t 1/2 )• The number of nuclear transformations of
a chain member Ui (t), is given by
Ui - F<11>. The keys - F<5> have
been discussed above and, completeness, are included briefly here. These keys are displayed at the bottom
of DCAL's main menu. Keys - can be displayed by pressing the space bar when the main
menu is active.
12.2.1 Help: Kev
The key displays a brief message regarding the function of the DCAL main menu item upon which the select
bar is positioned.
12.2.2 Active Case: Kev
This key displays the content of the $STEMNAM.DIR file which identifies the current or active case being
processed in an interactive manner. This key can be helpful if an interactive session has been interrupted.
12.2.3 =: kev
The biokinetic folder to be used in the calculations is displayed with the " =" label at the bottom of the
main menu display. This key can be used to select the biokinetic folder of interest or create a new folder. Note
the current folder will be used in both the interactive and batch sessions.
76
-------
12.2.4 =: key
The work folder which will contain output files created during the session is displayed with the "=" label
at the bottom of the main menu display. This key can be used to select a work folder or create a new folder.
Note the work folder will be used in both the interactive and batch sessions. The batch utility is selected from
DCAL's main menu looks for suitable input files (*.INP) in the work folder (see Chapter 6).
12.2.5 About: key
This key displays a list the authors of DCAL and the sponsor; the U.S. Environmental Protection Agency.
12.2.6 ACTINT Utility: Kev
This utility computes the number of nuclear transformations (Bq s) per Bq-intake over a 50-year period
following an intake of the parent radionuclide. The utility can be run following ACTACAL calculations. If the
user had requests that ACTACAL tabulate the activity as a function of time in the compartments (CPT file) as
well as in source regions (ACT file), then the utility will process both files and report the results in a single
output file. The name of the output file is composed of the root of the ACT file name with an extension U50.
If ACTACAL was run for a stable element (e.g., Ca), the utility tabulates the integral of the fraction of the
intake residing in the compartments in seconds. For example the integral might be considered as g-s per g intake
in the compartment or source region.
12.2.7 DRTINT Utility: Kev
This utility integrates the calculated dose rates following the intake over user defined time periods. Values for
the dose rate and committed dose are calculated by EPACAL, and the utility HTAB (available on the main
menu) provides a tabulation of the committed values (either absorbed or equivalent dose). DRTINT provides
additional capability by letting the user define the lower and upper time limits on the dose rate integral. The
integration times are specified in the DRTINT.INI file in the INI folder or by a DRTINT.INI file located in the
work folder. The former is referred to as the global INI file and the latter is the local INI file. The installed INI
file is listed below. The name given the output file has the root of the DRT or HRT file being processed with the
extension INT assigned.
DRTINT.INI
file defines the limits of
integration of the dose
rate files.
DRTINT is limited to 500
times in days.
START Input
<- Starting delimiter
0.0 1.0
1.0 2.0
2.0 3.0
0.0 3.0
0.0 30.0
0.0 365.0
0.0 18250.0
END Input
<- Ending delimiter
12.2.8 BIOTAB Utility: Kev
This utility tabulates the fraction of the intake expected to be excreted in 24-hr urine and fecal samples at
various times following an acute intake. In addition, the fraction of the activity retained in the body is also
tabulated. Data are presented for all members of the decay chain, all expressed in terms of a unit intake of the
parent member. If in response to ACTACAL's request for the name of the radionuclide only the chemical
symbol is given (DCAL's calculations are for the stable element) then BIOTAB's tabulation represents the
expected 24 h excretion and retention of the stable element. BIOTAB is applicable to both workers (adults) and
member of the public, including children. The urine (and fecal) excretion rates are derived by integrating over
77
-------
24 hr the product of the time-dependent contents of the urinary bladder (and lower large intestine) and its
removal rate constant. The fractional removal rate from the urinary bladder depends on age (or time) and
BIOTAB.INI provides the utility with the location of the ICRP67.BLD file containing these data. The name of
the output file is derived from the root of the ACT file with the extension EUD.
12.2.9 EXPORTM Utility: Kev
This utility will export the time dependent activity in CPT and ACT files and the time dependent dose rates in
DRT and HRT into an Excel spreadsheet. This utility remains under development at this time.
12.2.10 DcalSvs Utility: Kev
This function key invokes the utility DCALSYS.EXE which generates a listing of DCAL's executable files and
data libraries. The utility creates a file, DCALFILE.TXT, in DCAL's root folder. This file can be compared to
the file, DCALSYS.TXT, in the root folder which lists the files installed by the installation procedure. This
utility is provided as a mean to verify that DCAL's files have not been corrupted.
12.2.11 Manual: Kev
This key displays the pdf of this documentation. It is necessary the extension pdfhas been registered by
Windows to be opened by a suitable viewer; e.g., Adobe Acrobat Reader. Acrobat Reader can be obtained
from www.adobe.com.
78
-------
13. SUMMARY AND CONCLUSIONS
This version of the DCAL software has been used to prepare a number of federal guidance reports and
publications of the ICRP. Specifically, this release of the software is that used to produce Federal Guidance
Report 13 (EPA 1999). DCAL has demonstrated that a single PC-based software package would serve both
interactive and production calculations. Further development of DCAL is underway. Specifically this will
encompass:
• Development of a Windows version of the software.
• Inclusion of a more detailed treatment of gender,
• Inclusion of spontaneous fission within SEECAL,
• Consideration of chronic intakes,
• Inclusion of a module for calculation of deposition in respiratory tract,
• Inclusion of a module for evaluation of genetic risk,
• Addition of the risk modules into the menu.
In addition, updating of many of the data libraries is in progress:
• Updating the nuclear decay data files,
• Integrating information on bremsstrahlung into the nuclear decay files,
• Incorporating the year 2000 decennial cancer mortality data and life tables,
• Incorporating newer biokinetic data,
• Including newer SAF data for the various radiations.
Extension of DCAL to consider in utero exposures remains to be addressed. DCAL is expected to remain the
basis for the calculation of dose and risk by the Dosimetry Research Group and thus the software will remain
under active development.
79
-------
ACKNOWLEDGEMENTS
The authors would like to acknowledge the U.S. Environmental Protection Agency office of Radiation and
Indoor Air for their support in the development of the DCAL system. Particular thanks to Mike Boyd, Jerry
Puskin, and Neal Nelson of the office for their patience and encouragement as this software was developed.
Thanks are also extended to the Nuclear Regulatory Commission and the Department of Energy for their
support during the preparation of Federal Guidance Reports 12 and 13. DCAL includes computational modules
developed during the preparation of these reports.
We express our thanks to members of the Dose Calculational Task Group of Committee 2 of the International
Commission on Radiological Protection for numerous discussions regarding the implementation of ICRP
models, sharing of reference data files, and quality assurance reviews. These interactions contributed
significantly to DCAL development; however, the responsibility for any shortcomings lies with the authors.
We thank David Hyde of HydeSoft Computing, LLC (dplot.com), for graciously modifying the DPlot Jr
package to accommodate some specific needs within DCAL.
Final we thank Beth A. Eckerman of the Y-12 National Security Complex for her help with Microsoft Word and
editing of the document.
80
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REFERENCES
Birchall, A. and A. C. James. 1989. "A Microcomputer Algorithm for Solving First-Order Compartmental
Models Involving Recycling." Health Phys. 56, 857-868.
Cristy, M. and K. F. Eckerman. 1987. Specific Absorbed Fractions of Energy at Various Ages from Internal
Photon Sources. ORNL/TM-8381 /V1 -7. Oak Ridge National Laboratory, Oak Ridge, TN.
Cristy, M. and K. F. Eckerman. 1993. SEECAL: Program to Calculate Age-Dependent Specific Effective
Energies. ORNL/TM-12351, Oak Ridge National Laboratory, Oak Ridge, TN.
Eckerman, K. F., et al. 1993. Nuclear Decay Data Files of the Dosimetry Research Group. ORNL/TM-12350,
Oak Ridge National Laboratory, Oak Ridge, TN.
de Boor, C. A. 1978. Practical Guide to Splines. Applied Mathematical Sciences, Vol. 27. Springer-Verlag,
New York.
U. S. Environmental Protection Agency (EPA). 1993. External Exposure to Radionuclides in Air, Water, and
Soil, Federal Guidance Report 12. EPA-402-R-93-081, Oak Ridge National Laboratory, Oak Ridge, Tenn.; U.
S. Environmental Protection Agency, Washington, DC.
U. S. Environmental Protection Agency (EPA). 1994. Estimating Radiogenic Cancer Risks. EPA 402-R-93-076,
U. S. Environmental Protection Agency, Washington, DC.
U. S. Environmental Protection Agency (EPA). 1999. Cancer Risk Coefficients for Environmental Exposure to
Radionuclides, Federal Guidance Report 13. EPA-402/R-99-001, Oak Ridge National Laboratory, Oak Ridge,
Tenn.; U. S. Environmental Protection Agency, Washington, DC.
Fritsch, F. N. and J. A. Butland. 1982. A Method for Constructing Local Monotone Piecewise Cubic
Interpolants. UCRL-87559.
Fritsch, F. N. and R. E. Carlson. 1980. "Monotone Piecewise Cubic Interpolation," SIAMJ. Numer. Anal. 17,
238-246.
International Commission on Radiological Protection (ICRP). 1959. Report of Committee II on Permissible
Dose of Internal Radiation. ICRP Publication 2, Pergamon Press, Oxford.
International Commission on Radiological Protection (ICRP). 1975. Report of the Task Group on Reference
Man. ICRP Publication 23, Pergamon Press, Oxford.
International Commission on Radiological Protection (ICRP). 1979. Limits for Intakes by Workers. ICRP
Publication 30, Part 1, Pergamon Press, Oxford.
International Commission on Radiological Protection (ICRP). 1980. Limits for Intakes by Workers. ICRP
Publication 30, Part 2, Pergamon Press, Oxford.
International Commission on Radiological Protection (ICRP). 1981. Limits for Intakes by Workers. ICRP
Publication 30, Part 3, Pergamon Press, Oxford.
81
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International Commission on Radiological Protection (ICRP). 1983. Radionuclide Transformations Energy and
Intensity of Emission. ICRP Publication 38, Pergamon Press, Oxford.
International Commission on Radiological Protection (ICRP). 1988. Limits for Intakes by Workers: An
Addendum. ICRP Publication 30, Part 4, Pergamon Press, Oxford.
International Commission on Radiological Protection (ICRP). 1989. Age-Dependent Doses to Members of the
Public from Intake of Radionuclides, Part 1. ICRP Publication 56, Pergamon Press, Oxford.
International Commission on Radiological Protection (ICRP). 1991. 1990 Recommendations of the
International Commission on Radiological Protection. ICRP Publication 60, Pergamon Press, Oxford.
International Commission on Radiological Protection (ICRP). 1992. The Biological Basis for Dose Limitation
in the Skin. ICRP Publication 59, Pergamon Press, Oxford.
International Commission on Radiological Protection (ICRP). 1993. Age-Dependent Doses to Members of the
Public from Intake of Radionuclides, Part 2. ICRP Publication 67, Pergamon Press, Oxford.
International Commission on Radiological Protection (ICRP). 1994a. Human Respiratory Tract Model for
Radiological Protection. ICRP Publication 66, Pergamon Press, Oxford.
International Commission on Radiological Protection (ICRP). 1994b. Dose Coefficients for Intakes of
Radionuclides by Workers. ICRP Publication 68, Pergamon Press, Oxford.
International Commission on Radiological Protection (ICRP). 1995a. Age-Dependent Doses to Members of the
Public from Intake of Radionuclides, Part 3. ICRP Publication 69, Pergamon Press, Oxford.
International Commission on Radiological Protection (ICRP). 1995b. Age-Dependent Doses to Members of the
Public from Intake of Radionuclides, Part 4. ICRP Publication 71, Pergamon Press, Oxford.
International Commission on Radiological Protection (ICRP). 1996. Age-Dependent Doses to Members of the
Public fromlntake of Radionuclides, Part 5. Compilation of Ingestion and Inhalation Dose Coefficients. ICRP
Publication 72, Pergamon Press, Oxford.
Killough, G. G. and K. F. Eckerman. 1984. "A Conversational Eigenanalysis Program for Solving Differential
Equations," In: Computer Applications in Health Physics, 4.49-4.58. Proceedings ofthe 17th Midyear Topical
Symposium of the Health Physics Society. Eds. R. L. Kathren, D. P. Higby, and M. A. McKinney.
Kocher, D. C. and K.F. Eckerman. 1988. External Dose Rate Conversion Factors for Calculations of Dose to the
Public. DOE/EH-0070.
Leggett, R. W., D. E. Dunning, Jr., and K. F. Eckerman. 1984. "Modelling the Behaviour of Chains of
Radionuclides Inside the Body. Radiat. Prot. Dosim. 9, 77-91.
Leggett, R. W., K. F. Eckerman, and L. R. Williams. 1993. "An Elementary Method for Implementing
Complex Biokinetic Models. Health Phys. 64, 260-278.
National Center for Health Statistics (NCHS). 1992. Vital Statistics Mortality Data, Detail, 1989. NTIS order
number for data file tapes: PB92-504554, Hyattsville, MD.
82
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National Center for Health Statistics (NCHS). 1993a. Vital Statistics Mortality Data, Detail, 1990. NTIS order
number for data file tapes: PB93-504777, Hyattsville, MD.
National Center for Health Statistics (NCHS). 1993b. Vital Statistics Mortality Data, Detail, 1991. NTIS order
number for data file tapes: PB93-506889, Hyattsville, MD.
National Center for Health Statistics (NCHS). 1997. U. S. Decennial Life Tables for 1989-91, Vol. 1, No. 1.
DHHS, PHS-98-1150-1, Washington, DC.
Smith, B. T., et al. 1974. Matrix Eigensystem Routines-EISPACK Guide. Springer-Verlag, New York.
Weber, D. A., etal. 1989. MIRD: Radionuclide Data and Decay Schemes. Society of Nuclear Medicine, New
York.
83
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APPENDIX A
ANNOTATED LISTINGS OF DCAL OUTPUT FILES
This appendix contains an annotated set of DCAL's output files to highlight items that are critical to not only in
the user reviewing his calculations but also to quality assurance. The complete set of output files created by
DCAL's computational and utility modules are presented for the inhalation of 106Ru by a worker; the aerosol is
assumed to be characterized by and activity median aerodynamic diameter of 5 |_im and the chemical form is
that absorption Type F.
A.l File Rul06AF5.ACT: created by ACTACAL
l.ine identifies llie \ersion of
ACTACAI. used and the
dale lime of llie coni|HiUilion>
This is ACTACAL activity file Rul0 6AF5.act
« ACTACAL Ver. 8.3 (Jly 15, 2006) Jul
lex file:
LNG was:
F1 was:
ACTACAL exe file was:
Global ACTACAL INI file:
Global writing times file:
Global>,eomputational step file:
Global sS>«i£lard name file:
Global dec
LNG file rd
GF1 file rd
DEF file rd
RNL file rd
Age 0 mass f
Age 1 mass f
Age 5 mass f
Age 10 mass
Age 15 mass
Adult mass file rd by READMS was
END DIRECTORY INFO ON ACTACAL
0 19 2 127 7300 h
k00
368.2 d 5.0E-02 5
ime AI
^00F.+ 00 5 31R9F.-0?
ACTACAL.EXE
ACTACAL.INI
WRITIM.DAT
TIMIN.DAT
STDNAMES.TXT
ICRP38.NDX
ICRP66F.LNG
RU.GF1
18, 2006, at 11:05 »
404712 07-18-06 11:03a
2475 06-07-05
932 05-21-
449 02-28-
2789 01-18-
135919 02-28-
1541 02-28
215 02-28
580 02
(ilobal indicates lliese liles were
assigned h\ ACTACAI.'s l\l lile in
llie INI lolder
Si/.e (h\ les). dale,
and lime information
on each inpiii lile
used in llie
com|iulalions
12-28-03
12-28-03
1: OOp
1: OOp
REG"
1 7
Ru-10 6
Nuclid
Rn-1
i) comment lines. Il> source regions. 2
chain members. acli\il\ coni|-)uled al I27
limes, age in da\ of individual, and h
denoted mhalalion
I aue consider, aue 7.>< >( >d
Ru-10 6
Rh-10 6
Ru-10 6
Rh-10 6
Ru-10 6
Rh-10 6
Ru-10 6
Rh-10 6
Ru-10 6
Rh-10 6
Ru-10 6
Rh-10 6
3.000E-03 3 . 9402E-02
3.000E-03 3 . 9960E-02
4 . 000E-03 3 . 5 652E-02
4 . 000E-03 3 . 6233E-02
5.000E-03 3 . 2259E-02
5 . 000E-03 3 . 2 794E-02
5 . 000E-01 1. 0215E-2:
5.000E-01 0.0000E+0I
1. 000E+01 0 . 0000E+0I
1. 000E+01 0 . 0000E+0I
0E+00 F O
St_Cont
0.0000E+0
0.0000E+0
3.572 9E-02 .
2.3796E-02 .
6.4143E-02 .
5.7 968E-02 .
8.6588E-02 .
8.2 668E-02 .
1.0416E-01.
1.012 7E-01.
1.1777E-01.
1.573
Source regions
Parent nuclide. I I 2. f . WIAI). T\ |V.
occu|\ilional intake
6E-01..8.8403E-0 4..1.2 220E-0 4..
5E-01..8.3951E-04..1.1610E-0 4..
57E-01
00E+00
23E-01
48E-01
3E-01
-01
-01
-01
-01
01
8 . 178 8E-01
8.178 OE-01
Parent and daughler acli\ il\ (I$l|) as a
funclion of lime in llie source legions
follow ing an intake of I I5q
2 .250E+04 0.0000E+00L
2 . 250E+04 0 . 0000E+00..0.0 00 0E+0 0..0.C.
1. .3.0763E-03..6.4990E-01
1. .3.0 771E-03. . 6 . 4995E-01
1. .3.5 08 2E-0 4..1.735 7E-01
1. . 3.5093E-04..1.73 60E-01
0..0.0000E+00..0.0000E+00
)0. . 0 . 0000E+00..0.0000E+00
84
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A.2 File Rul06AF5.REQ: created by ACTACAL
This file provides the SEECAL module with the information needed to compute the relevant SEE values.
This is user request
..\.\dat\nuc\icrp38 ,
TITLE
« ACTACAL Ver. 8.3
END TITLE
NUCLIDES
Ru-106
Rh-106
END NUCLIDES
EQUIVALENT DOSE
TOTAL ONLY
AGE GROUPS
Adult Male
END AGE GROUPS
SOURCE REGIONS
AI
bbe-gel
bbe-sol
bbe-seq
BBi-gel
BBi-sol
BBi-seq
ET2-sur
ETl-sur
ET2-seq
LN-Th
LN-ET
St Cont
SI~Cont
Blood
ULI_Cont
LLI_Cont
Body Tis
UB_Cont
END SOURCE REGIONS
TARGET REGIONS
Adrenals
UB_Wall
Bone Sur
Brain
Breasts
//
I I
//
Ht_Wall
Uterus
END TARGET REGIONS
IdcnliTics llic nuclear dcca\ dala scl used
In A( T.\( AI. which SLLCAI. is in use
| Delimiter T]
;jly 15, 2006) 'Run jui m,—^uub,—ai, n:u3 »
Delimiter END TITLE
Delimiter NUCLIDES
Delimiter END NUCLIDES
Table type
Delimeter AGE GROUPS
Delimeter END AGE GROUPS
Delimeter SOURCE REGIONS
//
I I
//
Delimeter END SOUR
Delimeter TARGET REGIONS
I
| Delimeter END TARG
85
-------
A.3 File R11IO6HT.SEE: created by SEECAL
Note a similar file (RM06HT.SEE) is also created for the 106Rh daughter.
This is SEECAL file Rul06ht.SEE
« SEECAL Ver. 8.4 (Jly 15, 2006) Run Jul 18,
SEECAL exe file was: SEECAL.EXE
Global SEECAL INI file: SEECAL.INI
User request file was: RU106AF5.REQ
File with standard names was: STDNAMES.TXT
1 = number of age groups
Photon SAF file was: PSAFTXt
Electron-alpha AF file was:
Region mass file was:
2006, at 11:05
288080 07-15-06
1415 09-04-05
5158 07-18-06
2789 01-18-05
»
10:Ola
1: 23p
11:05a
3: 47p
l.isl ol'ilie lilesand llieir allrilniles
Ileum used In SLLCAI.
REGMAS; : .
1 = number of title lines, copied from fi
« ACTACAL Ver. 8.3 (Jly 15, 2006) Run
Following 3 lines identify the nuclide decay files
Index file was: ICRP38.NDX 135919 02-28-03
Radiation data file was: ICRP38.RAD 5971698 02-28-03
Beta spectrum data file was: ICRP38.BET 684882 02-28-03
'equivalent dose' = dose type (equivalent dose or absorbed dose)
'total only' = table type (full table, total only, or low-hi let)
'Ru-106 ',' 368.2 d ','B- ' = nuclide, half-life, decay mode
'n' 'n' 'y' 'n' 'n' 'n' = flags for Ph<10, Ph>=10, Beta, Elec, Alph
Age Group Name
'Adult Male '
19, 7, 3 = # of source regions, # of source regions/page, # of page
S. Region Masses (kg) for each age group, in order as above
1: OOp
1: OOp
1: OOp
a, SpFiss
s/age
0.00E+00
0 . 00E+00
//
I I
//
Hie ll> source legions established
In ACTACAI. lor which SI!l!
\allies are |iro\ ided
' AI
' bbe-gel
//
I I
//
'Body_Tis' 6.88E+01
'UB_Cont ' 1.20E-01
31 = number of target regions
T. Region Masses (kg) for each age group, in order as above
'Adrenals' 1.40E-02
4.50E-02
//
I I
//
3.30E-01
8.00E-02
Ihe 3 I lai'ijel organs lor which
SLL \ allies are lalmlaled
'UB_Wall
//
I I
//
'Ht_Wall
'Uterus
equivalent dose (Sv/nt) for Ru-106 & Age=Adult Male
P-
1 of 3
TARGETS RAD
SOURCE REGIONS
-AI
bbe-gel
bbe-sol bbe-seq
BBi-gel
BBi-sol
BBi-se
Adrenals
t
0.
0
0
0
0.0 0.
0
0.0
0.
0
0
0
UB Wall
t
0.
0
0
0
0.0 0.
0
0.0
0.
0
0
0
Bone Sur
t
0.
0
0
0
0.0 0.
0
0.0
0.
0
0
0
Brain
t
0.
0
0
0
~
-
~
~
~
0
0
Breasts
t
0.
0
0
0
0
0
St Wall
t
0.
0
0
0
1 .i|in\aieni (.lose (>\) 111 lartjel per ill 111
0
0
SI Wall
t
0.
0
0
0
source or ei|in\alenl dose rale (S\ s) 111
0
0
ULI Wall
t
0.
0
0
0
larsjel |vr 1 $l|
111 source
IViJ IOI1
0
0
LLI Wall
t
0.
0
0
0
0
0
Kidneys
t
0.
0
0
0
O
O
O
0
0
0
0
0
0
0
Liver
t
0.
0
0
0
O
O
O
0
0
0
0
0
0
0
ETl-bas
t
0.
0
0
0
O
O
O
0
0
0
0
0
0
0
ET2-bas
t
0.
0
0
0
O
O
O
0
0
0
0
0
0
0
LN-ET
t
0.
0
0
0
O
O
O
0
0
0
0
0
0
0
BBi-bas
t
0.
0
0
0
O
O
O
0
0.0
0
0
1
988E
BBi-sec
t
0.
0
0
0
O
O
O
0
4 .196E-17
1
589E-
15 7
447E
bbe-sec
t
6.
025E-22
4
898E-15
1. 737E-14 2
153E-15
O
O
0
0
0
0
AI
t
1.
461E-15
0
0
O
O
O
0
O
O
0
0
0
0
LN-Th
t
0.
0
0
0
O
O
O
0
O
O
0
0
0
0
Muscle
t
0.
0
0
0
O
O
O
0
O
O
0
0
0
0
86
-------
Ovaries
t
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
Pancreas
t
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
R Marrow
t
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
Skin
t
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
Spleen
t
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
Testes
t
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
Thymus
t
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
Thyroid
t
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
GB Wall
t
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
Ht Wall
t
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
Uterus
t
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
//
1 1
//
1 1
1 1
//
1 1
//
equivalent dose (Sv/nt) for Ru-106 & Age=Adult Male , p. 3 of 3
TARGETS RAD SOURCE REGIONS
Blood ULI_Cont LLI_Cont Body_Tis UB_Cont
Adrenals
t
2.335E-17
0
0
0
0
2 .335E-17
0
0
UB Wall
t
2.335E-17
0
0
0
0
2 .335E-17
6
696E
Bone Sur
t
2 .335E-17
0
0
0
0
2 .335E-17
0
0
Brain
t
2.335E-17
0
0
0
0
2 .335E-17
0
0
Breasts
t
2.335E-17
0
0
0
0
2 .335E-17
0
0
St Wall
t
2 .335E-17
0
0
0
0
2 .335E-17
0
0
SI Wall
t
2.335E-17
0
0
0
0
2 .335E-17
0
0
ULI Wall
t
2.335E-17
3
652E-15
0
0
2 .335E-17
0
0
LLI Wall
t
2 .335E-17
0
0
5
952E-15
2 .335E-17
0
0
Kidneys
t
2.335E-17
0
0
0
0
2 .335E-17
0
0
Liver
t
2 .335E-17
0
0
0
0
2 .335E-17
0
0
ETl-bas
t
2 .335E-17
0
0
0
0
2 .335E-17
0
0
ET2-bas
t
2.335E-17
0
0
0
0
2 .335E-17
0
0
LN-ET
t
2.335E-17
0
0
0
0
2 .335E-17
0
0
BBi-bas
t
2 .335E-17
0
0
0
0
2 .335E-17
0
0
BBi-sec
t
2.335E-17
0
0
0
0
2 .335E-17
0
0
bbe-sec
t
2.335E-17
0
0
0
0
2 .335E-17
0
0
AI
t
2 .335E-17
0
0
0
0
2 .335E-17
0
0
LN-Th
t
2.335E-17
0
0
0
0
2 .335E-17
0
0
Muscle
t
2.335E-17
0
0
0
0
2 .335E-17
0
0
Ovaries
t
2 .335E-17
0
0
0
0
2 .335E-17
0
0
Pancreas
t
2.335E-17
0
0
0
0
2 .335E-17
0
0
R Marrow
t
2.335E-17
0
0
0
0
2 .335E-17
0
0
Skin
t
2.335E-17
0
0
0
0
2 .335E-17
0
0
Spleen
t
2.335E-17
0
0
0
0
2 .335E-17
0
0
Testes
t
2.335E-17
0
0
0
0
2 .335E-17
0
0
Thymus
t
2.335E-17
0
0
0
0
2 .335E-17
0
0
Thyroid
t
2.335E-17
0
0
0
0
2 .335E-17
0
0
GB Wall
t
2.335E-17
0
0
0
0
2 .335E-17
0
0
Ht Wall
t
2.335E-17
0
0
0
0
2 .335E-17
0
0
Uterus
t
2.335E-17
0
0
0
0
2 .335E-17
0
0
87
-------
A.4 File R11IO6HT.SEE: created by EPACAL
This is EPACAL dose rate file Rul06AF5.hrt
« EPACAL Ver. 8.4 (Jly 15, 2006) Run Jul 18,
EPACAL exe file was: EPACAL.EXE
Global EPACAL ini file: EPACAL.INI
Global lung apportionment file: LUNGAS.DAT
Activity file was: RU10 6AF5.ACT
... Following info is from file RU106AF5.ACT:
« ACTACAL Ver. 8.3 (Jly 15, 2006) Run Jul 18,
ACTACAL exe file was:
Global ACTACAL INI file:
Global writing times file:
Global computational step file:
Global standard name :
Global decay data indj ¦
LNG file rd in subr.
GF1 file rd in subr.
ACTACAL.EXE
ACTACAL.INI
WRITIM.DAT
TIMIN.DAT
2 00 6, at 11:05 »
261656 07-15-06 9:58a
48 12-23-03 5:41p
357 09-04-05 5:03p
66203 07-18-06 11:05a
2 00 6, at 11:05 »
404712 07-18-06 11:03a
2475 06-07-05 10:45a
932 05-21-04 3:34p
449 02-28-03 l:00p
I.ISl
files and I hoi i" ill I ri liulcs used in llic ciilculiilions
END DIRECTORY INFO ON ACTACAL INPUT FILES
0 19 2 127 7300 h nTitle, nSOrg, nNuc, NumTim, ExpAge, InMode
1 7300
Ru-106 368.2 d 5.0E-02 5.0E+00 F O
19 = number of source organs
... End of info from file RU106AF5.ACT
Li|uiwik-nl dose liili- (S\.lI) 111 llii- adivikiIs per lh| ol
111 tiki- b\ ihc muli- specified 111 AC. I AC Al.
SEE input file was: RU106HT.SEE
SEE input file was:
. . . Following info is
« SEECAL Ver. 8.4
SEECAL exe file was:
Global SEECAL INI file: SEECAL.INI
User reguest file was: RU106AF5.REQ
File with standard names was: STDNAMES.TXT
1 = number of age groups
Photon SAF file was:
Electron-alpha AF file was
Region mass file was:
5158 07-18-06
2789 01-18-05
11
3
PSAFTX66.AM
ELALPHAF.AM
REGMASS.AM
1 = number of title lines, copied from file RU106AF5.REQ,
« ACTACAL Ver. 8.3 (Jly 15, 2006) Run Jul 18, 2006,
Following 3 lines identify the nuclide decay files
Index file was: ICRP38.NDX
Radiation data file was: ICRP38.RAD
Beta spectrum data file was: ICRP38.BET
... End of info from file RU106HT.SEE
... Following info is from file RH106HT.SEE :
« SEECAL Ver. 8.4 (Jly 15, 2006)
SEECAL exe file was:
Global SEECAL INI file:
User reguest file was:
File with standard names was:
RNL
file rd in subr. TIMEBLD
1: OOp
Age
0 mass file rd by READMS
was :
REGMASS.AO 0
3169
02-2E
-03
1: OOp
Age
1 mass file rd by READMS
was :
REGMASS.AO 1
2851
02-2E
-03
1: OOp
Age
5 mass file rd by READMS
was :
REGMASS.AO5
2849
02-2E
-03
1: OOp
Age
10 mass file rd by READMS
was :
REGMASS.A10
2850
02-2E
-03
1: 0 Op
Age
15 mass file rd by READMS
was :
REGMASS.Al5
2965
02-2 E
-03
1: 0 Op
Adult mass file rd by READMS
was :
REGMASS.AM
2995
02-2E
-03
1: 0 Op
14596 07-18-06 11:
271721 09-11-04 6:
2344 02-28-03 1:
2995 02-28-03 1:
that follow:
at 11:05 >>
135919 02-28-03 1:
5971698 02-28-03 1:
684882 02-28-03 1:
05a
05a
Ola
23p
05a
47p
57p
OOp
OOp
OOp
OOp
OOp
Run Jul 18
, 2006,
at
11:
: 05
>>
SEECAL.EXE
288080
07-
-15-
-06
10 :
: Ola
SEECAL.INI
1415
09-
-04-
-05
1:
: 2 3p
RU10 6AF5.REQ
5158
07-
-18-
-06
11:
: 05a
STDNAMES.TXT
2789
01-
-18-
-05
3 :
: 4 7p
ide decay files
ICRP38.NDX
135919
02-
-28-
-03
1:
O
O
ICRP38.RAD
5971698
02-
-28-
-03
1:
: OOp
ICRP38.BET
684882
02-
-28-
-03
1:
: OOp
Index file was:
Radiation data file was:
Beta spectrum data file was:
... End of info from file RH106HT.SEE
END HEADER RECORDS
7300.0 d, or 20.00 y = exposure age (from activity file)
127 = # of times (from activity file)
Time array, in days (from activity file):
88
-------
0.OOOE+OO 1.000E-03 2.000E-03 3.000E-03 4.000E-03 5.000E-03 6.000E-03 7.000E-03
8.000E-03 9.000E-03 1.000E-02 1.200E-02 1.400E-02 1.600E-02 1.800E-02 2.000E-02
2.300E-02 2 .600E-02 3.000E-02 3.500E-02 4.000E-02 4.500E-02 5.000E-02 6.000E-02
7.000E-02 8.000E-02 9.000E-02 1.000E-01 1.200E-01 1.400E-01 1.600E-01 1.800E-01
2.000E-01 2.300E-01 2.600E-01 3.000E-01 3.500E-01 4.000E-01 4.500E-01 5.000E-01
6.000E-01 7.000E-01 8.000E-01 9.000E-01 1.OOOE+OO 1.200E+00 1.400E+00 1.600E+00
1.800E+00 2.OOOE+OO 2.
5.OOOE+OO 6.OOOE+OO 7.'
1.600E+01 1.8OOE+Ol 2.
4.500E+01 5 . OOOE+Ol 6.
1. 400E+02 1.600E+02 1.
3 . 650E+02 3 . 670E+02 3.
8.000E+02 9.000E+02 1..
I.islmil: of the 127 11Hies ill which ACTACAI.
computed the ;icli\ il> in the source regions and the
limes ;it which llie dose rate will lie computed
"10 4 .500E+00
H 1.400E+01
4.000E+01
1.2 00E+02
3 .500E+02
7 . 000E+02
2 . 000E+03
2.300E+03 2.600E+03 3.000E+03 3.500E+03 4.000E+03 4.500E+03 5.000E+03 6.000E+03
7.000E+03 8.000E+03 9.000E+03 1.000E+04 1.100E+04 1.200E+04 1.300E+04 1.400E+04
1.500E+04 1.600E+04 1.700E+04 1.825E+04 1.950E+04 2.100E+04 2.250E+04
19 = # of source organs (from activity file; for info only). Source organs were:
AI bbe-gel bbe-sol bbe-seg BBi-gel BBi-sol BBi-seg ET2-sur
ETl-sur ET2-seg LN-Th LN-ET St_Cont SI_Cont Blood ULI_Cont
LLI_Cont Body_Tis UB_Cont
31 = # of target organs (from SEE files)
EQUIVALENT DOSE
eguivalent dose rates (Sv/d/Bq) at each time for each target organ follow:
Adrenals, t = equivalent dose rate (Sv/d/Bq) from Total radiations
0.0
1.272E-11 2.724E-11 3.802E-11 4.660E-11 5.367E-11 5.955E-11 6.445E-11
6.854E-11 7.196E-11 7.482E-11 7.922E-11
8.819E-11 8.878E-11 8.917E-11 8.929E-11
8.795E-11 8.758E-11
8.505E-11 8 . 457E-11 8.411E-11 8.349E-11
.232E-11 8.450E-11 8.605E-11 8.713E-11
.92 IE-11 8.903E-11 8 . 882E-11 8.837E-11
.725E-11 8.697E-11 8.648E-11 8.608E-11 8.571E-11 8.537E-11
.274E-11 8.201E-11
.131E-11 8.064E-11
7.941E-11 7.832E-11 7.736E-11 7.651E-11 7.574E-11 7.447E-11 7.338E-11 7.243E-11
7.159E-11 7.083E-11 6.978E-11 6.880E-11 6.758E-11 6.615E-11 6.480E-11 6.352E-11
6.228E-11 5.995E-11 5.779E-11 5.578E-11 5.390E-11 5.215E-11 4.899E-11 4.621E-11
4.377E-11 4.161E-11 3.969E-11 3.718E-11 3.505E-11 3.265E-11 3.019E-11 2.817E-11
2.648E-11 2 .502E-11 2.264E-11 2.074E-11 1.918E-11 1.787E-11 1.676E-11 1.503E-11
1.367E-11 1.259E-11 1.170E-11 1.095E-11 9.992E-12 9.175E-12 8.230E-12 7.214E-12
6.937E-12 6.901E-12 6.759E-12 6.335E-12 5.567E-12 4.893E-12 3.782E-12 2.923E-12
2.259E-12 1.746E-12 1.350E-12 8.064E-13 4.817E-13 2.878E-13 1.719E-13 1.027E-13
4.743E-14 2.190E-14 7.817E-15 2.156E-15 5.949E-16 1.641E-16 4.527E-17 3.445E-18
2.622E-19 1.995E-20 1.519E-21 1.169E-22 8.897E-24 6.770E-25 5.152E-26 3.921E-27
2.984E-28 2.271E-29 1.728E-30 6.908E-32 2 .\
Committed Dose (Sv/Bq) = 8.494E-09
// // //
II II II
//
//
//
Dose Rate
(Sv/d/Bq).
Standard
fc
4.180E-10
6.015E-10
7.049E-10
7 .
9.120E-10
9.142E-10
9.061E-10
8,
7.184E-10
6.680E-10
6.135E-10,
4.012E-10
3.918E-10
3.8 91EV>-
5 .310E-10
5 . 627E-10
5.974^10
6.
6.629E-10
6.436E-10
6 .194E-10
5 .
3.2 73E-10
2.705E-10
2 .250E-10
1.
7.527E-11
6 . 906E-11
6.515E-11
6.
4.5 90E-11
4.3 4 6E-11
4 . 031E-11
3 .
2.5 90E-11
2.328E-11
2 .12 IE^J.1
1.
1.2 62E-11
1.171E
L
9.
Committed ei|iu\iilenl dose in cidreimls
computed h> inleijmlinij the
ei|iu\alenldose rate
nder, ICRP 61
'2E-10 8 . 637E-10 8 . 884E-10
8.617E-10 8.333E-10 8.038E-10
<_ 10 5.298E-10 4.982E-10 4.508E-10
0 4 . 422E-10 4.686E-10
1.954E-11 1.815E-11 1.698E-11 1.515E-11
L 9.971E-12 9.148E-12 8.202E-12 7.187E-12
5.546E-12 4.875E-12 3.767E-12 2.912E-12
Normal (not split) form of the
remainder dose the colon received
the highest ei|iu\iilent dose
Ttrr;—equiv .—uuse idue. wunnai ruin
799E-13
926E-16
863E-24
7 42E-33
867E-13
635E-16
7 45E-25
756E-35 0
713E-13
510E-17
133E-26
0
023E-13
432E-18
906E-27
6. 91
2.25
4.72
2 . 61
2 . 97
Commi
Remaihui,—equiv .—uuse—idue . wuiniai—lunfiulation; Max weighted organ: Colon
1.889E-16 4.535E-11 5.808E-11 6.472E-11 7.001E-11 7.477E-11 7.916E-11 8.323E-11
8.704E-11 9.060E-11 9.393E-11 1.000E-10 1.054E-10 1.103E-10 1.147E-10 1.186E-10
1.239E-10 1.285E-10 1.338E-10 1.392E-10 1.436E-10 1.471E-10 1.498E-10 1.535E-10
1.554E-10 1.559E-10 1.554E-10 1.541E-10 1.502E-10 1.452E-10 1.399E-10 1.346E-10
89
-------
-11
-11
-11
-11
-11
-11
-13
-18
-27
Committed Dose (Sv/Bq) = 8.413E-09
A.5 File Rul06AF5.LOG: created by the DCAL Modules
The computational modules ACTACAL, SEECAL, and EPACAL all contribute to the log file for the
calculations. This file identifies the time stamp of the executables and all input files used during the course of
the calculations. Input files directed for use by the modules' INI file are referred to as "global" if they were
assigned by the modules INI file located in the folder DCALMNI or "local" if the INI file was present in the
work folder.
1.295E-10
8 . 648E-11
7 .2 61E-11
6 .161E-11
4 .323E-11
2 . 615E-11
1.350E-11
6 . 850E-12
2 .231E-12
4 . 683E-14
2.5 8 9E-19
2.946E-28
1.226E
8.357E
7.155E
5.92 6E
4.110E
2.471E
1.243E
6.814E
1.724E
2.163E
1.970E
2.242E
¦10 1.
¦11 8.
¦11 7.
¦11 5.
¦11
¦11
¦11
¦12
¦12
-14 7
-20
-29
165E-10
152E-11
013E-11
710E-11
92 0E-11
236E-11
155E-11
67 4E-12
333E-12
718E-15
499E-21
706E-30
1.098E-
7.996E-
6.887E-
5.511E-
3.672E-
2.048E-
1.081E-
6.255E-
7.962E-
2.129E-
1.154E-
6.821E-
1.
10
11 7
11 6
11 5
11 3
11 1
11 9
12 5
13 4
15 5
22
031E-10 9.792E-11 9.395E-11 9.087E
.8 7 0E-11 7.675E-11 7.515E-11 7.380E
. 739E-11 6.57 4E-11 6.425E-11 6.289E
. 325E-11 5.152E-11 4.839E-11 4.565E
.461E-11 3.22 4E-11 2.981E-11 2.782E
.894E-11 1.7 65E-11 1.655E-11 1.484E
.8 6" ------ -
Commilk-d ci.|ui\ak-nl dose In
.87 llie ivniainder nl'lissues
It
=5.724E-35 0.0
This is ACTACAL log file Rul0 6AF5.log
« ACTACAL Ver. 8.3 (Jly 15, 2006)
ACTACAL exe file was:
Global ACTACAL INI file:
Global writing times file:
Global computational step file:
Global standard name file:
Global decay data index file:
Activities written to file: Rul06AF5.act
Title lines (0) follow, if any:
Run Jul 18,
- 2006,
at
11:
: 05
»
ACTACAL.EXE
404712
07-
-18-
-06
11:
03a
ACTACAL.INI
2475
06-
-07-
-05
10:
45a
WRITIM.DAT
932
05-
-21-
-04
3:
34p
TIMIN.DAT
449
02-
-28-
-03
1:
o
o
STDNAMES.TXT
2789
01-
-18-
-05
3:
47p
ICRP38.NDX
135919
02-
-28-
-03
1:
OOp
Ru-106 Decay Chain:
Nuclide Halfli
1 Ru-106 368.
2 Rh-10 6 29.
Ru-106: Activity, T
Nuclide Tl/2
1 Ru-106 368
2 Rh-10 6 2 9
LNG file rd in subr
GF1 file rd in subr
DEF file rd in subr
RNL file rd in subr
Number of source
Half-lives and Branching Fractions
fe fl Nuclide f2 Nuclide
2d 1.0+00-> 2 Rh-106
9s
ransformations, & Cumulative Energies
A(t)/Ao intA/Ao(d) Ealpha
.2d 1. 3 74 62D-30 5 . 31200D+02
,9s 1.37463D-30 5.31200D+02
f 3
TIMELNG
TIMEF1
TIMEBIO
TIMEBLD
organs = 19
was :
was :
was :
was :
ICRP66F.LNG
RU.GF1
RU.DEF
ICRP67.BLD
(MeV) at
Ebeta
0.00E+00 5.31E+00
0.00E+00 7.56E+02
1541 02-28-03
215 02-28-
580 02-28-
Nuclide
lOOy
Egamma
0.00E+00
1.09E+02
331 02-28-
03
03
03
OOp
OOp
OOp
OOp
Source
Biokinetic
ai
<-
ai 1
bbe-gel
<-
bbe-gel
bbe-sol
<-
bbe-sol
bbe-seq
<-
bbe-seq
bbi-gel
<-
bbi-gel
bbi-sol
<-
bbi-sol
bbi-seq
<-
bbi-seq
et2-sur
<-
et2-sur
etl-sur
<-
etl-sur
et2-seq
<-
et2-seq
ln-th
<-
ln-th
ln-et
<-
ln-et
st cont
<-
st cont
si cont
<-
si cont
blood
<-
blood
uli cont
<-
uli cont
\lappiny ol
ivuions
biokiiK'lic coni|\ii'lmcnls and source
90
-------
lli_cont <- lli_cont
body_tis <- body_tis_a body_tis_b body_tis_c
ub cont <- ub cont
Age
Age
Age 0 mass file rd by READMS was: REGMASS.AOO
s file rd by READMS was: REGMASS.A01
s file rd by READMS was: REGMASS.A05
ss file rd by READMS was: REGMASS.A10
ss file rd by READMS was: REGMASS,A15
s file rd by READMS was: REGMASS.AM
Masses (kg) for reference age
1 mas
5 mas
Age 10 ma
Age 15 ma
Adult mas
Source
Region
AI
bbe-gel
bbe-sol
bbe-seg
BBi-gel
BBi-sol
BBi-seg
ET2-sur
ETl-sur
ET2-seg
LN-Th
LN-ET
St_Cont
SI_Cont
Blood
ULI_Cont
LLI_Cont
Body_Tis
UB_Cont
1 Ru-10
3169
02-2 £
3 — 03
1: 0 Op
2851
02-2 £
3 — 03
1: 0 Op
2849
02-2 £
3 — 03
1: 0 Op
2850
02-2 £
3-03
1: 0 Op
2965
02-2 £
3 — 03
1: 0 Op
2995
02-2 £
3-03
1: 0 Op
Newborn
1-y
5-y
10-y
15-y
Adult
0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+0
0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+0
0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+0
0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+0
0 . 01"
0.01
0.01
0.01
0.01
0.0U
\hisses iissitjned in source regions These
daUi are used lo define 1 he "Oilier" Isokinetic
compartment 11"present in Isokinetic model
0 . 00E+0
0 . 00E+0
0 . 00E+0
0 . 00E+0
0 . 00E+0
0 . 00E+0
0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+0
0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+0
1.06E-02 3.62E-02 7.51E-02 1.33E-01 1.95E-01 2.50E-0
2.03E-02 5.31E-02 1.06E-01 1.79E-01 3.22E-01 4.00E-0
0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+0
1.12E-02 2.87E-02 5.79E-02 9.75E-02 1.76E-01 2.20E-0
6.98E-03 1.83E-02 3.66E-02 6.17E-02 1.09E-01 1.35E-0
3.54E+00 9.54E+00 1.95E+01 3.26E+01 5.58E+01 6.88E+0
1.04E-02 2.60E-02 6.76E-02 7.80E-02 8.84E-02 1.20E-0
5 : Number of systemic compartments; excluding blood
0
0
0
0
0
0
0
0
0
0
0
0
1
1
0
1
1
1
1
= 1
Nuclide
Ru-106
Age(d)-->
Number
of compartments =
26
ai 1
( 1) "
->
bbe-gel
( 4
ai 1
( 1) "
->
blood
(17
ai 2
( 2) -
->
bbe-gel
( 4
ai 2
( 2) -
->
blood
(17
ai 3
( 3) -
->
bbe-gel
( 4
ai 3
( 3) -
->
ln-th
(13
ai 3
( 3) -
->
blood
(17
bbe-gel
( 4) -
->
bbi-gel
( 7
bbe-gel
( 4) -
->
blood
(17
bbe-sol
( 5) -
->
bbi-gel
( 7
bbe-sol
( 5) -
->
blood
(17
bbe-seg
( 6) -
->
ln-th
(13
bbe-seg
( 6) -
->
blood
(17
bbi-gel
( 7) -
->
et2-sur
(10
bbi-gel
( 7) -
->
blood
(17
bbi-sol
( 8) -
->
et2-sur
(10
bbi-sol
( 8) -
->
blood
(17
bbi-seg
( 9) -
->
ln-th
(13
bbi-seg
( 9) -
->
blood
(17
et2-sur
(10) -
->
st cont
(15
et2-sur
(10) -
->
blood
(17
etl-sur
(11) "
->
excreta
(24
et2-seg
(12) -
->
ln-et
(14
et2-seg
(12) -
->
blood
(17
ln-th
(13) -
->
blood
(17
ln-et
(14) -
->
blood
(17
st cont
(15) -
->
si cont
(16
si cont
(16) -
->
blood
(17
si cont
(16) -
->
uli cont
(18
blood
(17) -
->
uli cont
(18
blood
(17) -
->
body tis
a (20
blood
(17) -
->
body tis
b (21
7300
2.000E-02
1.000E+02
1.000E-03
1.000E+02
1.000E-04
2.000E-05
1.000E+02
2.000E+00
1.000E+02
3.000E-02
1.000E+02
1.000E-02
1.000E+02
1.000E+01
1.000E+02
3.000E-02
1.000E+02
1.000E-02
1.000E+02
1.000E+02
1.000E+02
1.000E+00
1.000E-03
1.000E+02
1.000E+02
1.000E+02
2.400E+01
3.158E-01
6.000E+00
6.932E-02
8.087E-01
6.931E-01
This listing. plus [lie in11uil
conditions noted below. is a
complete statement of the
compartment model that
ACTACAI. Ikis assembled
Note the transfer coefficients
( d) are for biological
processes.
91
-------
blood
(17)
-->
body tis
c (22)
4.621E-01
blood
(17)
-->
ub cont
(23)
2 . 773E-01
uli cont
(18)
-->
lli cont
(19)
1. 8 00E+00
Hi cont
(19)
-->
feces
(25)
1.000E+00
body tis
a (20)
-->
uli cont
(18)
1.733E-02
body tis
a (20)
-->
ub cont
(23)
6 . 932E-02
body tis
~b (21)
-->
uli cont
(18)
3.961E-03
body tis
b (21)
-->
ub cont
(23)
1.584E-02
body tis
c (22)
-->
uli cont
(18)
1.38 6E-04
body tis
c (22)
-->
ub cont
(23)
5.545E-04
ub cont
(23)
-->
urine
(26)
1.2 00E+01
Nuclide: Rh-106 Age(d)-->
Number of compartments = 2 6
7300
ai 1
1)
-->
bbe-gel
4)
2 . 000E-02
ai 1
1)
-->
blood
17)
1. 000E+02
ai 2
2)
-->
bbe-gel
4)
1. 000E-03
ai 2
2)
-->
blood
17)
1. 000E+02
ai 3
3)
-->
bbe-gel
4)
1. 000E-04
ai 3
3)
-->
ln-th
13)
2 . 000E-05
ai 3
3)
-->
blood
17)
1. 000E+02
bbe-gel
4)
-->
bbi-gel
7)
2 . 000E+00
bbe-gel
4)
-->
blood
17)
1. 000E+02
bbe-sol
5)
-->
bbi-gel
7)
3 . 000E-02
bbe-sol
5)
-->
blood
17)
1. 000E+02
bbe-seq
6)
-->
ln-th
13)
1. 000E-02
bbe-seq
6)
-->
blood
17)
1. 000E+02
bbi-gel
7)
-->
et2-sur
10)
1. 000E+01
bbi-gel
7)
-->
blood
17)
1. 000E+02
bbi-sol
8)
-->
et2-sur
10)
3 . 000E-02
bbi-sol
8)
-->
blood
17)
1. 000E+02
bbi-seq
9)
-->
ln-th
13)
1. 000E-02
bbi-seq
9)
-->
blood
17)
1. 000E+02
et2-sur
10)
-->
st cont
15)
1. 000E+02
et2-sur
10)
-->
blood
17)
1. 000E+02
etl-sur
11)
-->
excreta
24)
1. 000E+00
et2-seq
12)
-->
ln-et
14)
1. 000E-03
et2-seq
12)
-->
blood
17)
1. 000E+02
ln-th
13)
-->
blood
17)
1. 000E+02
ln-et
14)
-->
blood
17)
1. 000E+02
st cont
15)
-->
si cont
16)
2 . 400E+01
si cont
16)
-->
blood
17)
3 .158E-01
si cont
16)
-->
uli cont
18)
6 . 000E+00
blood
17)
-->
uli cont
18)
6.932E-02
blood
17)
-->
body tis
a
20)
8 . 087E-01
blood
17)
-->
body tis
>
21)
6 . 931E-01
blood
17)
-->
body tis
c
22)
4.621E-01
blood
17)
-->
ub cont
23)
2 . 773E-01
uli cont
18)
-->
lli cont
19)
1. 8 00E+00
lli cont
19)
-->
feces
25)
1.000E+00
body tis
a
20)
-->
uli cont
18)
1.733E-02
body tis
a
20)
-->
ub cont
23)
6 . 932E-02
body tis
b
21)
-->
uli cont
18)
3.961E-03
body tis
_b
21)
-->
ub cont
23)
1.584E-02
body tis
c
22)
-->
uli cont
18)
1.38 6E-04
body tis
c
22)
-->
ub cont
23)
5.545E-04
ub cont
23)
-->
urine
26)
1.2 00E+01
Number
of
source
regions =
19
Since shared kinetics is assumed
in illis case and lluis llns listing is
llie same as llial lor llie parenl
Nonzero initial conditions for
ai_l = 1.596E-02
ai_2 = 3 .191E-02
ai_3 = 5.319E-03
bbe-gel = 6.569E-03
bbe-sol = 4.384E-03
bbe-seq = 7.721E-05
bbi-gel = 1.171E-02
bbi-sol = 5 . 92IE-03
inhalation: AMAD = 5.000 asm
l.isluiij ol'coniiiarlmcnls Willi non/cro inilial
conditions. In llns case llie deposition in llie
ctniipai'lnieiils dI" llie luntj model assumes an
inlake of I lh| aerosol A\l.\l) 5
microns .
-------
bbi-seq = 1.243E-04
et2-sur = 3.989E-01
etl-sur = 3.385E-01
et2-seq = 1.996E-04
Total = 8.196E-01
Total number of transfers = 43
Compartments are exhausted, quit.
Calculations completed over 17496 cycles.
Data reported for 127 time steps.
Computational time (100s) = 39.
Computations ended normally.
SEECAL request file written: Rul06AF5.req
This is SEECAL loq file Rul0 6AF5.1oq
« SEECAL Ver. 8.4 (Jly 15, 2006) Run Jul
... Title lines from user request file follow:
« ACTACAL Ver. 8.3 (Jly 15, 2006) Run Jul
... End of title lines; number of title lines =
Quantity to be calculated = "equivalent dose"
Table type for SEE files = "total only"
Index iACalc; Aqe Group Name; Index iAqe
1 "adult male " 6
End of aqe qroup list; number of aqe qroups = 1
Index iSCalc; SOURCE Name; Index is
18, 2006, at 11:05 >>
18, 2006, at 11:05 »
1
1
"ai
33
2
"bbe-qel "
29
3
"bbe-sol "
30
4
"bbe-seq "
32
5
"bbi-qel "
25
6
"bbi-sol "
26
7
"bbi-seq "
28
8
"et2-sur "
21
9
"etl-sur "
20
10
"et2-seq "
23
11
"ln-th
34
12
"ln-et
24
13
"st cont "
10
14
"si cont "
12
15
"blood
58
16
"uli cont"
14
17
"Hi cont"
16
18
"body tis"
57
19
"ub cont "
2
End of source
Index iTCalc;
SLIX Al.'s inlornal imnskilion ol'ihc source
ivy ions clumck'i' iKinv. c y "hlv-ycl inlo ll
assigned inkier nulc\ in SAI's lllcs
reqion list;
TARGET Name;
number of
Index iT
sources = 19
1
"adrenals"
1
2
"ub_wall "
2
3
"bone sur"
3
4
"brain
4
5
"breasts "
5
6
"st wall "
6
7
"si wall "
7
8
"uli wall"
8
9
"lli_wall"
9
10
"kidneys "
10
11
"liver
11
12
"etl-bas "
12
13
"et2-bas "
13
14
"ln-et
14
15
"bbi-bas "
15
16
"bbi-sec "
16
17
"bbe-sec "
17
18
"ai
18
19
"ln-th
19
20
"muscle "
24
21
"ovaries "
25
22
"pancreas"
26
SLIX Al.'s inleiiiiil imnskilion ol'lhc mrycl
oiij;in lissuc cluir;iclcr luimc: c y "si wall' inlo llic
iissiunotl inlc^cr nulc\ in SAI's 1'ilcs
93
-------
23
"r marrow"
27
24
"skin
28
25
"spleen "
29
26
"testes "
30
27
"thymus "
31
28
"thyroid "
32
29
"gb wall "
33
30
"ht_wall "
34
31
"uterus "
35
End of target region list; number of targets = 31
SEE output file Rul06ht.SEE will be written.
SEE output file Rhl06ht.SEE will be written.
SEECAL exe file was:
SEECAL.EXE
288080
07-15-06
10:Ola
Global SEECAL INI file:
SEECAL.INI
1415
09-04-05
1: 23p
User reguest file was:
RU10 6AF5.REQ
5158
07-18-06
11:05a
File with standard names was:
STDNAMES.TXT
2789
01-18-05
3: 47p
Photon SAF file was:
PSAFTX66.AM
271721
09-11-04
6: 57p
Electron-alpha AF file was:
ELALPHAF.AM
2344
02-28-03
1: OOp
Region mass file was:
REGMASS.AM
2995
02-28-03
1: OOp
Index file was:
ICRP38.NDX
135919
02-28-03
1: OOp
Radiation data file was:
ICRP38.RAD
5971698
02-28-03
1: OOp
Beta spectrum data file was:
ICRP38.BET
684882
02-28-03
1: OOp
Photon SAF interpolation is linear
MAJOR PROGRAM LOOP: working on age # 1 (adult male) ...
Reading photon SAFs for age = adult male ...
Reading electron & alpha AFs for age = adult male ...
Calculating SEEs for nuclide = Ru-106 ...
for beta +/- particles (n= 1)
Calculating SEEs for nuclide = Rh-106 ...
for photons < 10 keV (n= 12)
for photons >= 10 keV (n= 168)
for beta +/- particles (n= 37)
for monoen. electrons (n= 987)
The following SEE files have been written:
RulO 6ht.SEE Rhl06ht.SEE
Program SEECAL ended normally.
This is EPACAL log file Rul06AF5.log
« EPACAL Ver. 8.4 (Jly 15, 2006) Run Jul 18, 2006, at 11:05 »
Activity data read from file Rul06AF5.act
All activity input files were opened successfully.
Dose rate output file Rul06AF5.hrt will be written
EPACAL exe file was: EPACAL.EXE 261656 07-15-06 9:58a
Global EPACAL ini file: EPACAL.INI 48 12-23-03 5:41p
Global lung apportionment file: LUNGAS.DAT 357 09-04-05 5:03p
Activity file was: RU106AF5.ACT 66203 07-18-06 11:05a
SEE data read from file Rul06ht.see
SEE data read from file Rhl06ht.see
All SEE input files were opened successfully
SEE input file was: RU106HT.SEE 14596 07-18-06 11:05a
SEE input file was: RH106HT.SEE 14596 07-18-06 11:05a
Reading headers of SEE files
Quant = eguivalent dose I.PA S lllcss;iL!CS IViJill'illIlL! ;i check nil lllc scl
Headers in all SEE files mr^ of laiucl oiuillis lISSHOS
Source organ names in acti'
**** Minor warning !
Target organ "GB^TJall " in the SEE files is not an organ used
in computing effective dose. It will appear in the dose rate output
files but will be ignored in computing effective dose. ****
94
-------
1 (RU10 6AF5.ACT)
**** Minor warning !
Target organ "Ht_Wall " in the SEE files is not an organ used
in computing effective dose. It will appear in the dose rate output
files but will be ignored in computing effective dose. ****
Exposure ages (days) in activity files are:
7300.0
Youngest age for SEE values to be read is: 7300 days (adult male/female)
MAJOR PROGRAM LOOP: working on activity file #
Reading SEE file for iNuc = 1 (Ru-106) ...
Reading activity file for iNuc =1 ...
Calculating dose rates for iNuc =1 ...
Reading SEE file for iNuc = 2 (Rh-106) ...
Reading activity file for iNuc =2 ...
Calculating dose rates for iNuc =2 ...
Writing dose rates to dose rate file # 1 (Rul
The following dose rate files have been written:
RulO 6AF5.hrt
Program EPACAL ended normally.
\olc nij coni|tk'lion of
IT \( \l. s ailcukilions.
A.6 File Rul06AF5.U50: created by ACTINT32
« ACTINT32 Ver.
ACTINT32 exe file
Activity file was
Number of times =
Number of
Number of
8.4 (July 15, 2006) --
was: ACTINT32.EXE
RU10 6AF5.ACT
127
nuclides = 2
source regions = 20
U50 (nt/Bg intake)
Region Ru-10 6 Rh-10 6
AI 4.596E+01 4.423E+01
bbe-gel 5.568E+00 5.355E+00
bbe-sol 3.787E+00 3.645E+00
bbe-seg 6.671E-02 6.420E-02
BBi-gel 9.301E+00 8.922E+00
BBi-sol 5.115E+00 4.922E+00
BBi-seg 1.074E-01 1.034E-01
ET2-sur 1.728E+02 1.604E+02
ETl-sur 2.919E+04 2.923E+04
ET2-seg 1.725E-01 1.660E-01
LN-Th 1.835E-05 1.830E-05
LN-ET 1.726E-06 1.722E-06
St_Cont 7.203E+02 7.193E+02
SI_Cont 2.735E+03 2.735E+03
Blood 1.088E+04 1.089E+04
ULI_Cont 1.140E+04 1.142E+04
LLI_Cont 2.048E+04 2.052E+04
Body_Tis 2.398E+06 2.401E+06
UB_Cont 1.375E+03 1.375E+03
Retained 2.475E+06 2.478E+06
Run
Jly 18,
4 7KB
65KB
2006, at
07-15-06
07-18-06
11:
11:
11:
05
49
05
Number of nuclear imnsl'onmilions (ill or Iit|-s)
of llic fuircnl and lis i.lnuijhk-1' in llic source
regions ;u.klrcssci.l in ilic file Rl l>
BIOTAB32 exe file was: BIOTAB32.EXE 58KB 07-18-06 10:50
Activity file was: RU106AF5.ACT 65KB 07-18-06 11:05
RulO6AF5.ACT: Inhalation: Age(d)=7300 Type=F f_l = 5.0E-02 AMAD(asm)=5.0E+00
Ru-10 6
E_f(t) E_u(t)
T(d) 24-h Cumulative 24-h Cumulative R_WB R_lung R_ET
0.0E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 8.196E-01 8.197E-02 7.376E-01
4 h 6.067E-04 6.067E-04 6.190E-03 6.190E-03 7.606E-01 4.550E-09 2.864E-01
8 h 4.899E-03 4.899E-03 1.499E-02 1.499E-02 7.033E-01 7.425E-16 2.424E-01
12 h 1.378E-02 1.378E-02 2.207E-02 2.207E-02 6.499E-01 1.266E-23 2.051E-01
95
-------
16 h
20 h
1. 0E+00
//
I I
//
4 . 0E+00
//
I I
//
1. 0E+01
//
I I
//
5.0E+01
//
I I
//
1.0E+03 6
//
I I
//
2.0E+04 0
Rh-106
613E-02 2. 613E-02 2.744E-02 2.744E-02 6.005E-01 0
052E-02 4.052E-02 3.155E-02 3.155E-02 5.552E-01 0
The acli\ il\ inl'ecal(L I") and nnnai\ (L n) excrelion al
\anons I lilies posl inlake as well as retention wilhin I ho
whole IhkK (R \\ IJ). luiiij (R Inny) and in the
e\lralhoracic aii\\a> (R IT) lor iIk- paivnl
l.
//
I I
//
565E-
//
I I
//
175E-
//
I I
//
000E+00
-04
-07
//
I I
//
2 . 283E-01 5.986E
//
I I
//
2.368E-01 2.463E
//
I I
//
0 . 000E+00
//
I I
//
-04 1.570E-01
//
I I
//
06 1.900E-01 4
//
I I
//
0 . 000E+00 0 . 000E+00
//
I I
//
8.254E-
//
I I
//
433E-
//
I I
//
4.127E-
000E+00
000E+00
000E+00
//
I I
//
pOOE+OO
//
I I
//
300E+00
//
I I
//
02 0.000E+00
//
I I
//
03 0.000E+00
//
I I
//
24 0 . 000E+00
T(d)
0.0E+00 0
4 h
8 h
12 h
16 h
20 h
1. 0E+00
//
I I
//
4 . 0E+00
//
I I
//
1.0E+01
//
I I
//
5.0E+01
//
I I
//
1. 0E+03
//
I I
//
2.0E+04 0
E_f(t) -
2 4-h Cumulative
, 000E+00 0.000E+00 0.
048E-04 6.048E-04 6.
893E-03 4.893E-03 1.
377E-02 1.377E-02 2.
612E-02 2.612E-02 2.
050E-02 4.050E-02 3.
,573E-02 5.573E-02 3.
// //
E_u(t)
2 4-h Cumulative R_WB
000E+00 0.000E+00 0.000E+00
181E-03 6 .181E-03 7.606E-01
498E-02 1.498E-02 7.033E-01
206E-02 2.206E-02 6.500E-01
743E-02 2.743E-02 6.005E-01
155E-02 3.155E-02 5.552E-01
478E-02 3.478E-02 5.141E-01
// //
IIk-acli\il\ in local (L I") and unnai\ (L u) cxcivIioikiI
unions limes |iosl inlakc as well as-acliviiy wilhin the
whole hod> (R W'li). Innij (R Inny) and in llie
eMralhoiacic airwa\ (R I! I) olihe danyhler lor a llk|
iniake ol'the |iarenl . • • •
6.
II II
// //
566E-04 2.287E-01
// //
II II
// //
182E-07 2.372E-01 2.464E
// //
II II
// //
000E+00 0 . 000E+00
II II
// //
986E-04 1.571E-01 8.255E-02
// //
II II
// //
06 1. 901E-01 4 . 439E-03
// //
II II
// //
0.000E+00 0.000E+00 4.181E-24
R_lung
0 . 000E+00
4. 626E-09
7.548E-16
0.000E+00
0.000E+00
0.000E+00
0.000E+00
//
I I
//
|)00E+00
//
I I
//
t00E+00
//
I I
//
0 . 000E+00
//
I I
//
0 . 000E+00
//
I I
//
0 . 000E+00
1. 736E-01
1. 469E-01
1.243E-01
//
I I
//
6.153E-03
//
I I
//
1.508E-05
//
I I
//
5.942E-23
//
I I
//
0 . 000E+00
//
I I
//
0 . 000E+00
R_ET
0 . 000E+00
2 . 865E-01
2 . 424E-01
2 . 051E-01
1. 736E-01
1. 469E-01
1.243E-01
//
I I
//
6.181E-03
//
I I
//
1.515E-05
//
I I
//
5.969E-23
//
I I
//
0 . 000E+00
//
I I
//
0 . 000E+00
A.8 File Rul06AF5.HEF: created by HTAB32 utility
Ru-106 Inhalation Committed Equivalent Dose Coefficients (Sv/Bq): Type: F, AMAD = 5.0 asm
20 Year
f_l 0.05
Adrenals 8.49E-09
Bladder Wall 9.78E-09
Bone Surfaces 8.47E-09
Brain 8.33E-09
Breast 8.29E-09
GI-Tract
96
-------
St Wall
SI Wall
ULI Wall
LLI Wall
Kidneys
Liver
Resp. Tract
ET Region
Lung
Muscle
Ovaries
Pancreas
Red Marrow
Skin
Spleen
Testes
Thymus
Thyroid
G Bladder
Heart
Uterus
Remainder
Effective Dose
8.7 6E-09
9.30E-09
1.44E-08
2.59E-08
8.4 6E-0 9
8.4 6E-0 9
1.20E-08
8.42E-09
8 .39E-09
8.5 6E-0 9
8.52E-09
8 . 44E-09
8 .2 6E-09
8.45E-09
8.39E-09
8.43E-09
8.43E-09
8.49E-09
8.48E-09
8.54E-09
8.41E-09
9.87E-09
SuniniaiN ol'llie com milled dose coefficients The
coefficients lor llic wirious regions in llie limy can lv
lisled is llic user so indiailcs when MTAIJ32 is invoked
value (s) marked by
are based on splitting of remainder weight.
Output file: Rul06AF5.hef
« HTAB32 Ver 8.4 (July 18, 2006) Run Jly 18, 2006, at 11:11 »
HTAB32 exe file was: HTAB32.EXE 52kb 07-18-06 10:45
Dose rate file was : RU106AF5.HRT 55kb 07-18-06 11:05
A.9 File Rul06AF5.INT: created by the ACTINT32 utility
Ver 8.4 (July 15, 2006) Run Jly 18, 2
« DRTINT32
DRTINT32 exe file was:
Dose rate file was:
Global INI File was:
Nuclide: Ru-106 Tl/2 =
DRTINT32.EXE
RU10 6AF5.HRT
DRTINT.INI
368.2 d
53kb
55kb
lkb
00 6, at 11:05 »
07-16-06 18:28
07-18-06 11:05
07-18-06 10:54
Intake mode: Inhalation
Type = F 0 fl = 5.0E-02
AMAD = 5.0E+00 um
Age at intake = 7300.0 d
Number of times = 127
Number of target regions = 35
Max time in dose rate ta,
Eguivalent Dose
I he ei|ui\
ivriod I I
in llie ulolx
llenl (.lose in
lo
T2 I he i nley
DRUM i\i
lui'ijel orpins o\ er I he
mlion limes are defined
Hie
T1
0.000E+00
1.000E+00
2.000E+00
0 . 000E+00
0.000E+00
0.000E+00
T2 (d)
1. 000E+00
2 . 000E+00
4 . 000E+00
4 . 000E+00
3.650E+02
1.825E+04
ake at
Adrenals
8 . 076E-11
7 . 302E-11
1.353E-10
2.891E-10
5.803E-09
8.494E-09
+ 04 d
time 0)
UB_Wall
3.243E-10
1.561E-10
2 . 37 4E-10
7.178E-10
7.069E-09
9. 777E-09
ET_Reg
2.436E-
8.2 43E-
5.120E-
3.772E-
9.299E-
1.197E-
Lung_66 Remaindr Effective
09 1.089E-10 1. 0 HE-10 6.071E-10
10 7.256E-11 7.467E-11 4.532E-10
10 1. 339E-10 1. 351E-10 3.860E-10
09 3 .154E-10 3 .109E-10 1.446E-09
09 5.765E-09 5.756E-09 7.190E-09
08 8 .424E-09 8.413E-09 9.870E-09
97
-------
APPENDIX B
ANNOTATED LISTINGS OF DCAL BATCH OUTPUT FILES
This appendix contains an annotated set of DCAL's files created during a batch calculation of risk for an
inhalation intake. DCAL's batch mode of operation was discussed in Section 6.0.
B.l EXAMPINH.INP File
This is the example batch input file in the folder DCAL\WRK\WORK2. This file was run through DCAL using
the biokinetic data in the folder DCAL\DAT\BIO\F13.
I.isl ol'codes in
r:ilriil:ilmns
order lhe\ are In Iv run in
End of listing of codes
Start list of case files to be deleted
DCAL example batch input file for inhalation.
******* nn S ffffffff ffffffff aaaa t 1.0E-02 ffffffff <-- Comments >
BATCH CODES <- Delimited starting list of code
ACTACAL.EXE
SEECAL.EXE
EPACAL.EXE
RISKCAL.EXE
END CODES
DELETE CASE FILES
* . SEE
* .REQ
* .LOG
* .ACT
* . DRT
END DELETE
GLOBAL INPUT
Dose_Type
Intake_Route
Exposure_Type
Default_Amad
#_Ages_at_intake 6
100 365 1825 3650 5475 7300
END GLOBAL INPUT
CASE INPUT DATA
in batch
I.isl of 1'iles lo Iv deleled as calculation c\cle
a fun e sequence ol codes
muiuh llie
Absorbed_Dose
Inhalation
Environmental
1.0
End of case files to be deleted.
Start of global input for cases
S|vcilicalion ol'ihe exposure silualion
H-3
H H20
F
H-3
H H20
V
H-3
H H20
G
Be- 7
F
C-14
C Org
F
C-14
C CO
G
C-14
C C02
G
Na-24
F
S-35
S Inorg
F
S-35
S Inorg
V
S-35
S Org
V
Sr-90
9125
F
Tc-99
F
1-131
1
F
1-131
1
V
1-131
1
V
Th-232
I
9125
M
U-238
I
9125
F
U-238
I
9125
M
Pu-23 9
9125
M
Pu-23 9
9125
S
<
<
1.0
End of global case input
Start of case data
H20Vapor
HGas
C02GAS
S02Gas
CS2Gas
IVapor
IMethyl
Nuclide cases lo Iv
processed see
Seel (v
B.2. EXAMPINH.HDB File
The *.HDB file is created by EPACAL and lists the calculated committed dose coefficients. The type of
coefficient (absorbed or equivalent) depends on the specification in the batch input file (* .INP). Since the input
98
-------
file EXAMPINH.INP is computing risk coefficients, RISKCAL.EXE included among the batch code listing, the
coefficients are committed absorbed dose and hence values are given for low and high LET - see the Th-232
data below. Coefficients are included in the full table for equivalent dose to the remainder and the effective dose
(Sv/Bq) but these are only presents for possible QA purposes.
Inhalation Dose Coefficients: Committed Absorbed Dose per Unit Intake (Gy/Bq)
Nuclide
Aqe
AMAD
Type/f1
Ad r e n a1s .
Thyroid
Lunq 66
. Biokinetic
.Date |
H-3
100
1 . 0E+00
F E
1 . 0E+00
1
L
2.457E-11.
2 . 457E-11.
2 .
482E-11
. H H20.
DEF
.07-20-06
H-3
365
1 . 0E+00
F E
1 . 0E+00
1
L
1.921E-11.
1. 921E-11.
1.
938E-11
. H H20.
DEF
. 07-20-06
H-3
1825
1 . 0E+00
F E
1 . 0E+00
1
L
1.074E-11.
1.074E-11.
1.
083E-11
. H H20.
DEF
. 07-20-06
H-3
3650
1 . 0E+00
F E
1 . 0E+00
1
L
7.993E-12.
7.993E-12.
8 .
044E-12
. H H20.
DEF
.07-20-06
H-3
5475
1 . 0E+00
F E
1 . 0E+00
1
L
5.827E-12 .
5 . 827E-12.
5.
860E-12
. H H20.
DEF
.07-20-06
H-3
7300
1 . 0E+00
F E
1 . 0E+00
1
L
6.159E-12.
6.159E-12.
6 .
186E-12
. H H20.
DEF
.07-20-06
H-3
100
0 . 0E+00
V E
1 . 0E+00
1
L
6.347E-11.
6.347E-11.
6 .
347E-11
. H H20.
DEF
. 07-20-06
//
//
//
//
//
//
//
//
//
//
//
//
//
//
//
//
//
//
//
//
1-131
100
1 . 0E+00
F E
1 . 0E+00
1
L
1.959E-10.
1. 434E-06.
3.
887E-10
. I.DEF
07-20-06
1-131
365
1 . 0E+00
F E
1 . 0E+00
1
L
1.399E-10.
1. 426E-06.
3.
006E-10
. I.DEF
07-20-06
1-131
1825
1 . 0E+00
F E
1 . 0E+00
1
L
6.390E-11.
7 . 294E-07.
1.
642E-10
. I.DEF
07-20-06
1-131
3650
1 . 0E+00
F E
1 . 0E+00
1
L
3.813E-11.
3 . 7 05E-07.
1.
106E-10
. I.DEF
07-20-06
1-131
5475
1 . 0E+00
F E
1 . 0E+00
1
L
1. 993E-11.
2 . 232E-07.
7 .
310E-11
. I.DEF
07-20-06
1-131
7300
1 . 0E+00
F E
1.0E+00
1
L
1 . 691E-11.
1 . 469E-07.
5.
956E-11
. I.DEF
07-20-06
//
//
//
//
//
//
//
//
//
//
//
//
//
//
//
//
//
//
//
//
1-131
100
0 . 0E+00
V E
1 . 0E+00
1
L
3.328E-10.
2.597E-06.
5.
084E-10
. I.DEF
07-20-06
1-131
365
0 . 0E+00
V E
1 . 0E+00
1
L
2.324E-10.
2 . 52 9E-06.
3.
853E-10
. I.DEF
07-20-06
1-131
1825
0 . 0E+00
V E
1 . 0E+00
1
L
1.208E-10.
1. 4 63E-06.
2 .
300E-10
. I.DEF
07-20-06
1-131
3650
0 . 0E+00
V E
1 . 0E+00
1
L
7.17 0E-11.
7.395E-07.
1.
484E-10
. I.DEF
07-20-06
1-131
5475
0 . 0E+00
V E
1 . 0E+00
1
L
4.113E-11.
4 . 834E-07.
8 .
859E-11
. I.DEF
07-20-06
1-131
7300
0 . 0E+00
V E
1.0E+00
1
L
3.372E-11.
3.067E-07.
7 .
243E-11
. I.DEF
07-20-06
//
//
//
//
//
//
//
//
//
//
//
//
//
//
//
//
//
//
//
//
Th-232
100
1 . 0E+00
M E
5. 0E-03
2
L
7 . 827E-08.
5.847E-08.
8 .
797E-08
. TH.DEF
07-20-06
H
7 . 865E-07.
7 . 865E-07.
5.
318E-06
$
Th-232
365
1 . 0E+00
M E
5.0E-04
2
L
8 . 319E-08.
6 .145E-08.
8 .
648E-08
. TH.DEF
07-20-06
H
7 . 765E-07.
7.765E-07.
4 .
261E-06
$
Th-232
1825
1 . 0E+00
M E
5.0E-04
2
L
8 . 009E-08.
5.719E-08.
7 .
217E-08
. TH.DEF
07-20-06
H
5.77 5E-07.
5.77 5E-07.
2 .
753E-06
$
Th-232
3650
1 . 0E+00
M E
5.0E-04
2
L
7.436E-08 .
5.195E-08.
6 .
080E-08
. TH.DEF
07-20-06
H
4.216E-07.
4.216E-07.
1.
8 6 0E-0 6
$
Th-232
5475
1 . 0E+00
M E
5.0E-04
2
L
7.090E-08 .
4.892E-08.
5.
568E-08
. TH.DEF
07-20-06
H
3.608E-07.
3.608E-07 .
1.
557E-06
$
Th-232
9125
1 . 0E+00
M E
5.0E-04
2
L
5.137E-08 .
3.565E-08.
4 .
253E-08
. TH.DEF
07-20-06
H
3.330E-07 .
3.330E-07 .
1.
356E-06
$
B.3. EXAMPINH.TAB File
The * .TAB file, written by RISKCAL.EXE, is a compact listing of the mortality and morbidity risk coefficients.
This output file was used to create the tables in Federal Guidance Report 13.
Mortality and Morbidity Risk Coefficients (per Bq intake)
Nuclide
Tl/2
AMAD
Type/f1
Mortality
Morbidity
H-3
12 .35
y
1.000
F
1.0E+00
3.61E-13
5.28E-13
H-3
12 .35
y
0 .000
V
1.0E+00
1.04E-12
1.52E-12
H-3
12 .35
y
0 .000
G
1.0E+00
1.04E-16
1.52E-16
Be-7
53.3
d
1.000
F
5.0E-03
2.17E-12
3.12E-12
C-14
5730
y
1.000
F
1.0E+00
1.15E-11
1.68E-11
C-14
5730
y
0 .000
G
1.0E+00
6.14E-14
9.09E-14
C-14
5730
y
0 .000
G
1.0E+00
3.68E-13
5.39E-13
Na-24
15 .00
h
1.000
F
1.0E+00
8.94E-12
1.28E-11
S-35
87 .44
d
1.000
F
8.0E-01
3.93E-12
6.28E-12
S-35
87 .44
d
0 .000
V
8 . 0E-01
8.63E-12
1.34E-11
S-35
87 .44
d
0 .000
V
8 . 0E-01
5.3 0E-11
7.85E-11
99
-------
Sr-90
29. 12
y
1. 000
F
3.0E-01
1.08E-09
1.17E-09
Tc-99
2.13E5
y
1. 000
F
8.0E-01
1.86E-11
3.14E-11
1-131
8 . 04
d
1. 000
F
1.0E+00
5.55E-11
5.27E-10
1-131
8 . 04
d
0. 000
V
1.0E+00
1.48E-10
1.36E-09
1-131
8 . 04
d
0. 000
V
1.0E+00
1.10E-10
1.06E-09
Th-232
1. 405E10
y
1. 000
M
5.0E-04
5.18E-07
6.45E-07
U-238
4 . 468E9
y
1. 000
F
2.0E-02
1.09E-08
1.54E-08
U-238
4 . 468E9
y
1. 000
M
2.0E-02
2.38E-07
2.52E-07
Pu-239
24065
y
1. 000
M
5.0E-04
7.94E-07
9.00E-07
Pu-239
24065
y
1. 000
S
1.0E-05
8.45E-07
8.96E-07
B.4. EXAMPINH.RBS File
The *.RBS file, written by RISKCAL.EXE, list the mortality and morbidity risk coefficients within age
groupings (defined in the GROUPS.DAT file in the folder DCAL\DAT\RSK). Only the panel of the mortality
risk coefficients is shown below. The tables in Federal Guidance Report 13 gave only the total mortality
coefficients for the 0-110 age group. Note the value for H-3 Type F below (3.6 IE-13) corresponds to that list in
the EXAMPINH.TAB table above. See the discussion following the annotated listing regarding the nature of the
coefficients for the age groups.
Mortality and Morbidity Risk Coefficients: Risk
Sel nl'cancers
considered
Nuclide AMAD Type/fl Cancer
H-3 1.000 F E 1.0E+00 esophagus
stomach
colon
liver
lung
bone
skin
breast
ovary
bladder
kidney
thyroid
leukemia
residual
Total
//
I I
//
//
I I
//
Be- 7
//
I I
//
Pu-23 9
0-
2 .06E-
1.29E-
4 . 89E-
2.64E-
3.33E-
1.68E-
3.01E-
1.78E-
2.68E-
3.82E-
9.21E-
1.24E-
1.19E-
4.69E-
1.8 6E-
5
14 1.
13 7.
13 2.
14 1.40E-14
13 1.
15 8.
15 1.
13 9.
14 1.
14 2.
15 4.
14 5.
13 4.
13 2.
12 9.
per Unit Intake (/Bq)
Mortality
1.000 F E 5.0E-03 esophagus
stomach
colon
liver
lung
bone
skin
breast
ovary
bladder
kidney
thyroid
leukemia
residual
Total
//
I I
//
1.000 S E 1.0E-05 esophagus
stomach
colon
liver
1.14E
4 . 8 0E
4 .5 4E
1.42
2 .11
2.7
1.4!
7.0!
2.4;
2.0!
6.1'
6.2<
1.6:
3 ,5<
1.39
7.8 6E
3.09E
1.10E
7.99E
¦13 4.
¦13 2.
-12 2.
5- 15 15- 25
07E-14 8.24E-15
38E-14 6.34E-14
48E-13 1.06E-13
1.13E-14
74E-13 7.20E-14
75E-16 6.84E-16
39E-15 9.05E-16
10E-14 4.57E-14
37E-14 9.86E-15
03E-14 1.66E-14
86E-15 3.93E-15
77E-15 2.78E-15
60E-14 2.79E-14
45E-13 1.86E-13
50E-13 5.55E-13
//
I I
//
86E-14 2.83E-14
73E-13 1.89E-13
15E-12 7.21E-13
04E-14
25- 70
7.07E-15
1. 42E-14
1.96E-14
9.69E-15
3.82E-14
5.82E-16
4.48E-16
1.41E-14
8.33E-15
1.60E-14
3.31E-15
1. 02E-15
3.69E-14
4.72E-14
2.17E-13
2.31E-14
4.02E-14
1.26E-13
3.31E-14
L.54E-13
Risk coefficient li\ cancer l\ |V and ;
group I he coeflicienls ie|H'esenl llie
conlnlnilion in risk during lliese ages
lor a cohort of new horns See Ivlow.
0-110
7.2 8E-15
2 . 8 7E-14
6.51E-14
9.86E-15
6.04E-14
6.11E-16
6.25E-16
2.90E-14
8.72E-15
1.59E-14
3 .38E-15
1.94E-15
3.65E-14
9.26E-14
3 . 61E-13
//
I I
//
2 . 65E-14
9.22E-14
5.16E-13
3 . 68E-14
2.8 8E-13
15
iue
-10 4.78E-10 3.53E-10 1.42E-10
-09 1.57E-09 8.04E-10 1.58E-10
-08 4.00E-09 1.26E-09 3.00E-10
-08 6.17E-08 5.75E-08 2.55E-08
2.06E-10
4 .50E-10
1.05E-09
3 .22E-08
100
-------
lung
bone
skin
breast
ovary
bladder
kidney
thyroid
leukemia
residual
Total
4.83E-06
1.62E-08
7.42E-11
2.04E-09
5.24E-09
1.57E-09
8.79E-10
2.60E-10
3.97E-09
1.16E-08
4.96E-06
2.3 9E-0 6
1.55E-08
3.66E-11
8.59E-10
4.18E-09
1.01E-09
5.35E-10
1.09E-10
2.40E-09
5.3 6E-0 9
2.4 8E-0 6
8.44E-07
1.65E-08
2.30E-11
3.74E-10
3.27E-09
8.28E-10
4.45E-10
5.44E-11
2.64E-09
2.76E-09
9.31E-07
4.99E-07
7.78E-09
6.96E-12
9.60E-11
1.31E-09
3.74E-10
2 .2 4E-10
1.80E-11
1.50E-09
4.71E-10
5.37E-07
7.96E-07
9.17E-09
1.31E-11
2.50E-10
1.82E-09
4.92E-10
2 . 78E-10
3. 64E-11
1.67E-09
1.52E-09
8.45E-07
The risk coefficients represent the mortality experience of the age groups of a cohort of newborns. To derive a
coefficient applicable to individuals enter the age group (xl - x2); that is, survived to the age xl, the coefficient
should be divided by .S'(x 1) where .S'(x 1) is the value of the survival function at age x 1. For example, the lifetime
lung cancer mortality risk for individuals of age 25-70 is 4.99E-07 / 0.97671 where 0.97671 is the survival to
age 25 (see file SURV90E.DAT in folder DCAL\DAT\RSK) which yields 5.11E-07 Bq 1.
B.4 RSKRSK.RSK File
The * .RSK file, written by RISKCAL.EXE, list the mortality and morbidity risk coefficients for each nuclide by
cancer, age, and gender. This can be a rather large file.
Mortality (/Bq) Morbidity (/Bq)
Male Female Both
2.44E-14 5.38E-14 3.87E-14
1.93E-14 4.24E-14 3.06E-14
1.60E-14 3.53E-14 2.54E-14
1.36E-14 3.00E-14 2.16E-14
1.08E-14 2.37E-14 1.71E-14
1.08E-14 2.37E-14 1.71E-14
9.99E-15 2.20E-14 1.59E-14
9.39E-15 2.07E-14 1.49E-14
8.92E-15 1.96E-14 1.41E-14
8.04E-15 1.77E-14 1.28E-14
8.04E-15 1.77E-14 1.27E-14
// // //
II II II
// // //
11 6.75E-15 1.49E-14 1.07E-14 7.50E-15 1.65E-14 1.19E-14
12 6.25E-15 1.38E-14 9.92E-15 6.95E-15 1.53E-14 1.10E-14
13 5.79E-15 1.27E-14 9.19E-15 6.44E-15 1.42E-14 1.02E-14
14 5.28E-15 1.16E-14 8.37E-15 5.86E-15 1.29E-14 9.31E-15
15 5.28E-15 1.16E-14 8.38E-15 5.87E-15 1.29E-14 9.31E-15
16 5.25E-15 1.16E-14 8.33E-15 5.84E-15 1.28E-14 9.26E-15
17 5.27E-15 1.16E-14 8.36E-15 5.86E-15 1.29E-14 9.29E-15
18 5.34E-15 1.17E-14 8.47E-15 5.94E-15 1.30E-14 9.41E-15
19 5.61E-15 1.23E-14 8.88E-15 6.23E-15 1.37E-14 9.87E-15
20 5.61E-15 1.23E-14 8.89E-15 6.24E-15 1.37E-14 9.88E-15
// // //
II II II
// // //
100 1.48E-18 7.51E-18 6.32E-18 1.64E-18 8.35E-18 7.02E-18
101 9.43E-19 4.64E-18 3.94E-18 1.05E-18 5.16E-18 4.38E-18
102 5.81E-19 2.74E-18 2.35E-18 6.45E-19 3.04E-18 2.61E-18
103 3.42E-19 1.53E-18 1.33E-18 3.80E-19 1.70E-18 1.48E-18
104 1.92E-19 8.13E-19 7.11E-19 2.13E-19 9.03E-19 7.89E-19
105 1.01E-19 4.06E-19 3.58E-19 1.12E-19 4.51E-19 3.98E-19
106 4.96E-20 1.89E-19 1.68E-19 5.51E-20 2.10E-19 1.87E-19
107 2.23E-20 8.06E-20 7.22E-20 2.47E-20 8.96E-20 8.03E-20
108 8.92E-21 3.08E-20 2.78E-20 9.91E-21 3.42E-20 3.09E-20
109 3.02E-21 9.98E-21 9.06E-21 3.36E-21 1.11E-20 1.01E-20
Age
Male
Female
Both
H-3
1.000
F E 1.0E+00
Cancer site: e
isophagus
0
2 .19E-14
4.84E-14
3.49E-14
1
1.73E-14
3.82E-14
2 . 75E-14
2
1.44E-14
3.18E-14
2.2 9E-14
3
1.23E-14
2.70E-14
1.95E-14
4
9.71E-15
2.14E-14
1.54E-14
5
9.71E-15
2.14E-14
1.54E-14
6
8 . 99E-15
1.98E-14
1.43E-14
7
8.45E-15
1.86E-14
1.34E-14
8
8 . 02E-15
1.77E-14
1.27E-14
9
7.23E-15
1.59E-14
1.15E-14
10
7 .23E-15
1.59E-14
1.15E-14
101
-------
110 2.78E-22 8.84E-22 8.06E-22 3.09E-22 9.82E-22 8.95E-22
Cancer site: stomach
0 1.67E-13 3.34E-13 2.48E-13 1.86E-13 3.71E-13 2.76E-13
1 1.19E-13 2.38E-13 1.77E-13 1.33E-13 2.65E-13 1.97E-13
2 9.65E-14 1.92E-13 1.43E-13 1.07E-13 2.14E-13 1.59E-13
3 8.03E-14 1.60E-13 1.19E-13 8.93E-14 1.78E-13 1.33E-13
4 6.2IE-14 1.24E-13 9.22E-14 6.90E-14 1.38E-13 1.02E-13
5 6.2IE-14 1.24E-13 9.22E-14 6.90E-14 1.38E-13 1.02E-13
6 5.69E-14 1.13E-13 8.46E-14 6.33E-14 1.26E-13 9.40E-14
7 5.30E-14 1.06E-13 7.88E-14 5.89E-14 1.17E-13 8.75E-14
8 4.99E-14 9.95E-14 7.42E-14 5.55E-14 1.11E-13 8.24E-14
9 4.44E-14 8.84E-14 6.59E-14 4.93E-14 9.83E-14 7.32E-14
10 5.83E-14 1.01E-13 7.92E-14 6.48E-14 1.12E-13 8.80E-14
// // //
11 II II
// // //
Cancer site: colon
0 6.87E-13 1.02E-12 8.50E-13 1.25E-12 1.86E-12 1.55E-12
1 5.33E-13 7.91E-13 6.59E-13 9.69E-13 1.44E-12 1.20E-12
2 4.40E-13 6.53E-13 5.44E-13 8.00E-13 1.19E-12 9.89E-13
// // //
II II II
// // //
Cancer site: liver
0 5.38E-14 3.52E-14 4.47E-14 5.66E-14 3.70E-14 4.71E-14
1 4.25E-14 2.77E-14 3.53E-14 4.47E-14 2.92E-14 3.71E-14
// // //
II II II
// // //
Cancer site: lung
0 4.37E-13 6.99E-13 5.65E-13 4.60E-13 7.36E-13 5.94E-13
1 3.44E-13 5.50E-13 4.45E-13 3.63E-13 5.79E-13 4.68E-13
// // //
II II II
// // //
Cancer site: bone
0 2.83E-15 2.85E-15 2.84E-15 4.04E-15 4.07E-15 4.06E-15
1 2.23E-15 2.24E-15 2.24E-15 3.19E-15 3.20E-15 3.20E-15
// // //
II II II
// // //
Cancer site: skin
0 5.02E-15 5.58E-15 5.29E-15 5.02E-15 5.58E-15 5.29E-15
1 3.90E-15 4.34E-15 4.11E-15 3.90E-15 4.34E-15 4.11E-15
// // //
II II II
// // //
Cancer site: breast
0 0.00E+00 6.16E-13 3.01E-13 0.00E+00 1.23E-12 6.01E-13
1 0.00E+00 4.86E-13 2.37E-13 0.00E+00 9.71E-13 4.74E-13
// // //
II II II
// // //
Cancer site: ovary
0 0.00E+00 9.30E-14 4.54E-14 0.00E+00 1.33E-13 6.48E-14
1 0.00E+00 7.33E-14 3.58E-14 0.00E+00 1.05E-13 5.11E-14
2 0.00E+00 6.10E-14 2.98E-14 0.00E+00 8.72E-14 4.26E-14
// // //
II II II
// // //
Cancer site: bladder
0 8.63E-14 4.19E-14 6.46E-14 1.73E-13 8.38E-14 1.29E-13
1 6.8IE-14 3.30E-14 5.10E-14 1.36E-13 6.61E-14 1.02E-13
// // //
II II II
// // //
Cancer site: kidney
102
-------
0 1.89E-14 1.20E-14 1.56E-14 2.91E-14 1.85E-14 2.40E-14
1 1.50E-14 9.49E-15 1.23E-14 2.30E-14 1.46E-14 1.89E-14
// // //
II II II
// // //
Cancer site: thyroid
0 1.37E-14 3.02E-14 2.18E-14 1.37E-13 3.02E-13 2.18E-13
1 1.07E-14 2.35E-14 1.69E-14 1.07E-13 2.35E-13 1.69E-13
// // //
II II II
// // //
Cancer site: leukemia
0 2.04E-13 1.88E-13 1.96E-13 2.06E-13 1.90E-13 1.98E-13
1 1.64E-13 1.48E-13 1.56E-13 1.65E-13 1.50E-13 1.58E-13
// // //
II II II
// // //
Cancer site: residual
0 6.49E-13 9.46E-13 7.94E-13 9.15E-13 1.33E-12 1.12E-12
1 5.13E-13 7.45E-13 6.26E-13 7.22E-13 1.05E-12 8.82E-13
// // //
II II II
// // //
Cancer site: Total
0 2.35E-12 4.07E-12 3.19E-12 3.44E-12 6.36E-12 4.86E-12
1 1.83E-12 3.17E-12 2.49E-12 2.69E-12 4.95E-12 3.79E-12
// // //
II II II
// // //
103
-------
APPENDIX C
DCAL LIMITING DIMENSIONS
This appendix summarizes the limiting dimensions of the parameters in potential user prepared input files. In
most instances DCAL's modules are dimensions are of sufficient size to readily accommodate any reasonable
size problem the user might prepare. In Tables C. 1 - C.4 detail the restrictions place on specific data elements.
Tables C.5 - C.7 address restrictions within the major computational modules.
Table C.l Restrictions on Compartment Model Definition
Description
Limit
Module
Biokinetic compartments
90
ACTACAL
Transfers from any compartment
60
ACTACAL
Total transfers in model
240
ACTACAL
Ages specified in systemic model
10
ACTACAL
Anatomical source regions
60
SEECAL
Table C.2 Restrictions on Decay Chain Definition
Description
Limit
Module
Chain members
30
ACTACAL
SEECAL
Branching fractions for any member
3
ACTACAL
SEECAL
RADSUM32
CHAIN32
Table C.3 Restrictions on Emitted Radiations
Description
Limit
Module
Radiations
4000
SEECAL
Branching fractions for any member
3
ACTACAL
Table C.4 Restrictions within ACTACAL
Description
Biokinetic compartments
Transfers from any compartment
Total transfers in model
Ages specified in systemic model
Anatomical source regions
Anatomical target regions
Particle sizes in ICRP 66 lung model
Age-specific phantoms
Activity f(t)
Limit
90
60
240
10
60
37
15
6
150
104
-------
Table C.5 Restriction within SEECAL
Description
Limit
Age-specific phantoms
8
Anatomical source regions
60
Anatomical source regions
37
Nuclides
30
Table C.6 Restriction within EPACAL
Description
Limit
Age-specific phantoms
6
Anatomical source regions
60
Anatomical target regions
37
Nuclides
20
LET
2
Table C.7 Restriction within RISKCAL
Description Limit
Age-specific absorbed dose rates 10
Anatomical target regions 37
Cancer types 12
Years in life table 120
LET 2
105
-------
APPENDIX D
NUCLEAR DECAY DATA FILES
The Dosimetry Research Group (DRG) of the Life Science Division at Oak Ridge National Laboratory (ORNL)
has for several years maintained data bases of nuclear decay data for use in dosimetric calculations. Although
other sources of such information are available, the ORNL database, in machine-readable form, has been
explicitly designed to address the needs in medical, environmental, and occupational radiation protection. This
release of DCAL contains the nuclear decay data collection initially documented in ORNL/TM-12350
(Eckerman et al. 1993). The collection denoted as "ICRP38" collection consists of data for 825 radionuclides that
appeared in Publication 38 (ICRP 1983), plus an additional 13 radionuclides evaluated during the preparation of
a monograph for the Medical Internal Radiation Dose (MIRD) Committee of the Society of Nuclear Medicine
(Weber et al. 1989). The collection is located in the folder \DCAL\DAT\NUC\.
The ICRP38 nuclear data collection consists of three data files. The triplet of files has the root name "ICRP38"
with extensions NDX, RAD, and BET. The ICRP38.NDX file is an index file that serves as the entry into the
other two larger files. The file ICRP38.RAD contains data on the unique or average energy and the intensity of
each emitted radiation while the file ICRP38.BET contains, for beta emitters, the beta spectra. The NDX file
contains one record for each nuclide. The nuclide record has fields giving the location of the nuclide records (and
the number of such records) in the RAD and BET files. In addition to the pointers, other fields of the NDX
record give the half-life, the mode of decay, the identity of any radioactive decay products (daughters), the
fraction of the transformation forming the daughters (the branching fractions), and the total energy emitted by
alpha, electron, and photon radiations (excluding electrons and photons accompanying spontaneous fission). The
NDX records are sorted by the nuclide field so DCAL's modules can use a binary search to locate the record for
the nuclide of interest. While the purpose of the NDX file was to provide entrance into the two other larger files,
its records are of considerable utility in their own right. For example, the modules ACTACAL and CHAIN
construct the decay chain for a radionuclide and determine possible truncation of the chain based on information
in the NDX file.
In some instances, a radionuclide is not uniquely identified by its atomic number (or chemical symbol) and mass
number. Nuclei of the same atomic and mass numbers, but with distinguishable nuclear properties, are referred
to as isomers. Identification of an isomer requires reference to it physical half-life. In DCAL, these nuclei are
identified by the nonstandard notation listed in Table D.l.
Some changes were introduced into the NDX and RAD files since the publication of ORNL/TM-12350 to
enable DCAL's SEECAL module to access directly the nuclear decay data. Specifically, the RAD file records
for each nuclide have been sorted by radiation type and by increasing energy within each radiation type with
additional pointers added to the NDX file to enable accessing the data. Table D.2 lists the current content of the
nuclide records in NDX. As noted above, the NDX file was sorted by the nuclide field such that a binary search
is used by DCAL's modules to locate the data for a given nuclide. The fields nl through n5 were added to
enable the location of specific radiation types. The nl field gives the number of photons of energy less than
10 keV (SEECAL treats these photons as non penetrating radiations). If the radionuclide of interest is an alpha
emitter, n5 is greater than zero; the RAD record for the lowest energy alpha particle emitted by the nuclide
is irad + n\ + n2 + n3 + n4 +1 where irad is record number of the nuclide in the RAD file, nl the number of
photons of energy less than 10 keV, n2 is the number of photons of energy equal to or greater than 10 ke V, n3 is
the number of beta lines (their average energy is contained in the RAD file), and n4 is the number of discrete
electrons. Since irad is the header record of the nuclide in the RAD file, not its first data record, it is necessary
to add 1 as noted. The following code fragment illustrates the reading of the n5 alpha records in the RAD file.
The format of the records in the RAD file is given in Table D.3
106
-------
irec = irad + nl + n2 + n3 + n4
do i = 1, n5
Read(20, ' (il,2E12.0)rec = irec + i) icode, f(i), e(i)
end do
The RAD records for photons (x- and gamma rays), discrete electrons (Auger and internal conversion
electrons), beta particles, and alpha particles have been sorted by increasing energy. This sorting facilitated the
procedure used to interpolate the specific absorbed fraction data.
The direct-access files ICRP38.BET and MIRD.BET contain the beta spectra data for the beta emitters in these
collections. The spectral data were computed on a fixed energy grid, to facilitate tabulation of the composite
87
spectra; i.e., summed over all beta transitions. Fig. D. 1 illustrates the composite spectra for Kr. The structure
of the records is given in Table B.4. For each nuclide, the header record gives the name of the nuclide. The
header is followed by a record containing the end-point energy of the spectrum, in MeV. The subsequent data
records contain the frequency N (!•'.) (number of betas per MeV per decay) at the standard energy grid points that
are less than the end-point energy. The very last record is the frequency at the nuclide-unique end-point energy.
The number of beta particles per decay Y is
Y = J N(E) dE
(Dl)
and the average energy of the spectrum is
i GO
E = — J EN(E)dE
1 0
(D.2)
DCAL's CHAIN and RADSUM utilities can also be used to examine the data for a specific radionuclide.
cu
0.5
0.4 - j
25
0.3
1
>
QJ
S °-2
0.1
0.0 I I I I I I I I '—I—1—I—I—Ll_i
0.0 0.5 1.0 1.5 2.0 2.5 J.O 3.5 4.0
E (MeV)
Fig. D-l. Spectrum of beta particles emitted by Kr-87.
107
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REFERENCES
Eckerman, K. F., et al. 1993. Nuclear Decay Data Files of the Dosimetry Research Group. ORNL/TM-
12350, Oak Ridge National Laboratory, Oak Ridge, TN.
International Commission on Radiological Protection (ICRP). 1983. Radionuclide Transformations Energy and
Intensity of Emission. ICRP Publication 38, Pergamon Press, Oxford.
D. A. Weber, et al. 1989. MIRD: Radionuclide Data and Decay Schemes. Society of Nuclear Medicine, New
York.
Table D.l. Isomers with nonstandard naming convention"
Nuclide
Tl/2
Decay Mode
Radioactive Daughters and Branching Fractions
Eu-150a
12.62h
B- EC B+
Eu-150b
34.2y
EC
In-110a
69.1m
EC B+
Ir-186a
15.8h
EC B+
Ir-186b
1.75h
EC B+
Ir-190m
1.2h
IT
Ir-190n
3. lh
IT EC
Nb-89a
66m
EC B+
Zr-89
1.00
Nb-89b
122m
EC B+
Zr-89
1.00
Np-236a
115E3y
EC B-
Pu-236
0.089 U-236 0.911
Np-236b
22.5h
B-EC
Pu-236
0.48 U-236 0.52
Re-182a
12.7h
EC B+
Re-182b
64. Oh
EC
Sb-120a
15.89m
EC B+
Sb-120b
5.76d
EC
Sb-124m
93s
IT B-
Sb-124
0.80
Sb-124n
20.2m
IT
Sb-124m
1.00
Sb-128a
10.4m
B-
Sb-128b
9.01h
B-
Ta-178a
9.31m
EC
Ta-178b
2.2h
EC
Tb-156m
24.4h
IT
Tb-156
1.00
Tb-156n
5.Oh
IT
Tb-156
1.00
"The MIRD collection contains only the Ir-190 isomers. The collection does contain the 9.31m Ta-178 isomer but
not the Ta-178b isomer.
108
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Table D.2. Structure of data records in NDX file
Variable Format Description (records 2 and beyond)3
Head record
il, i2 (2i4) number of first (2) and last data records
Data Records (2,lastf
Nuclide
A7
Name of nuclide; e.g., Am-241, Tc-99m
Half-life
A8
Half-life of nuclide
Units
A2
Half-life units: us-microseconds, ms-milliseconds, s-seconds
m-minutes, d-day, and y-year.
Decay
Mode
A8
A, B-, B+, EC, IT, & SF denote alpha, beta minus, beta plus, electron
capture, internal transition, and spontaneous fission.
Irad
17
Record number of nuclide in RAD file
Nrad
15
Number of records for nuclide in RAD file
Ibet
16
Record number of nuclide in BET file
Nbet
14
Number of records for nuclide in BET file
jl
14
Record number of first daughter in NDX file
F1
El 1.0
Branching fraction forming first daughter
j2
14
Record number of second daughter in NDX file
F2
El 1.0
Branching fraction forming second daughter
j3
14
Record number of third daughter in NDX file
F3
El 1.0
Branching fraction forming third daughter
Ea
F7.0
Total energy of alpha emissions (MeV/nt)
Ee
F8.0
Total energy of electron emission (spectra and discrete) (MeV/nt)
Ep
F8.0
Total energy of photon emissions (MeV/nt)
nl
14
Number of photons of energy less than lOkeV per nt
n2
14
Number of photons of energy equal or greater than 10 keV per nt
n3
14
Number of beta lines with reported average energies per nt
n4
15
Number of discrete electron emitted per nt
n5
14
Number of alpha particles emitted per nt
Spf
13
Spontaneous fission flag
Mass
111
Atomic mass
Date
A10
Date of ENSDF evaluation
aFORMAT(a7,a8,a2,a8,i7,i5,i6,i4,3(i4,E11.0),e7.0,2f8.0,3i4,i5,i4,i3,ill,al0) record length = 160
109
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Table D.3.
Structure of records in RAD files
Variable
Format
Description
Nuclide head recordsa
Nuclide
a7
Name of nuclide; e.g., Am-241, Tc-99m
Half-life
al3
Half-life of nuclide
Nrad
i5
Number of records for this nuclide
Data records (nrad records for nuclide)"
Icode
il
Code for radiation type (see below)
Y (%)
el2.0
Yield in % per nt
E(MeV)
el2.0
Unique or average energy of radiation
Icode
Mnemonic6
Description
1
G
Gamma rays
2
X
x-rays
3
Aq
Annihilation photons
4
b+
Beta + particles
5
b-
Beta - particles
6
ic
Internal conversion electrons
7
ae
Auger electrons
8
a
Alpha particles
9
Spontaneous fission
"Record length = 25.
aDEXRAX uses the following mnemonics for radiations associated with spontaneous fission: ff -
fission fragments, n - neutrons, pg - prompt gamma rays, dg - delayed gamma rays, sb - beta
emissions.
Table D.4. Structure of records in BET files
Variable
Format
Description
Head record (record ibct)"
Nuclide
A7
Name of nuclide; e.g., Am-241
Data records
F
-^max
Y(E)
f9.0
e9.0
End-point energy of spectrum
Value of differential energy spectrum (1, ..., nbet values)
"Record length =
9.
110
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