KKRL 71-3
RADIOLOGICAL SURVEY
AROUND POWER PLANTS
USING FOSSIL FUEL
ENVIRONMENTAL I'koiKCl io\ \i.K\o
Office of Research and Monitoring
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EASTERN ENVIRONMENTAL RADIATION LABORATORY
TECHNICAL REPORTS
Technical reports of the Eastern Environmental Radiation Lab-
oratory are available from the National Technical Information Service,
Springfield, Va. 22151, when a PB number is indicated after the title.
Microfiche copies are $0.95; prices for paper copies are indicated
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The PB number should be cited when ordering.
BRH/SERHL 70-1
RO/EERL 71-1
EERL 71-2
EERL 71-3
Title
Radiological Survey of Major California Nuclear Ports
(April 1967) (PB 178 728 $6.00)
Radiological Survey of Hampton Roads, Virginia
(January 1968) (AD 683 208 $6.00)
Laboratory Examination of a Ruptured 50-mg
Radium Source (May 1970) (PB 191 810 $3.00)
Development of Ion Exchange Processes for the
Removal of Radionuclides from Milk (January 1971)
(PB 198 052 $0.50)
Investigation of Tritiated Luminous Compounds
(June 1971)
Radiological Survey Around Power Plants Using
Fossil Fuel (July 1970)
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EERL 71-3
RADIOLOGICAL SURVEY
AROUND POWER PLANTS
USING FOSSIL FUEL
by
P. H. Bedrosian
RESEARCH DIVISION
and
D. G. Easterly
S. L. Cutnmings
EASTERN ENVIRONMENTAL RADIATION LABORATORY
Post Office Box 61
Montgomery, Alabama 36101
July 1970
ENVIRONMENTAL PROTECTION AGENCY
Office of Research and Monitoring
Radiation Research
Rockville, Maryland, 20852
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FOREWORD
The Environmental Protection Agency has the responsibility of
carrying out a national program for measuring the population exposure
to ionizing and nonionizing radiation and for assessing the radio-
logical quality of the environment.
The Eastern Environmental Radiation Laboratory (EERL) contributes
to this program through research, applied technology, and training.
These endeavors include the development of analytical and radiochemical
methodology and the planning and presentation of courses on the radio-
logical health aspects of ionizing and nonionizing radiation.
Until December 1970, the EERL was part of the Department of Health,
Education, and Welfare and was known as the Southeastern Radiological
Health Laboratory. At that time, pursuant to the President's Reorgani-
zation Plan No. 3, the Laboratory was transferred from the Bureau of
Radiological Health, DHEW, to the newly created Environmental Protection
Agency and given its present designation.
The technical reports of the EERL provide a rapid and comprehensive
means for publishing results of intramural and contractor projects. The
reports are distributed to regional, State, and local radiological health
agencies, to universities and libraries, to other government and private
agencies, and to interested individuals. Readers are encouraged to send
their comments on the material contained in these reports to the Office
of Research and Monitoring.
William A. Mills, Ph.D.
Acting Chief
Radiation Research
iii
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PREFACE
Contributions of radioactive materials to the environment arise
from sources other than those associated with the nuclear industry.
One such source is the steam power plant burning fossil fuel,
including oil and particularly coal. These facilities release fly
ash, which contains radionuclides such as uranium, radium and
thorium and which represents a source of radiation exposure to man.
This report considers the environmental radioactive contribu-
tion related to selected fossil-fuel-burning steam power plants.
Emphasis has been placed on a single coal-burning installation and
the sampling techniques used to obtain data for estimating radiation
exposure to man.
Charles R. Porter
Director
Eastern Environmental Radiation
Laboratory
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CONTENTS
Page
FOREWORD [[[
PREFACE [[[ v
LIST OF TABLES ............................................. vii
LIST OF FIGURES ............................................ viii
ABSTRACT [[[ ix
THE AUTHORS ................................................. x
INTRODUCTION ............................................... 1
SURVEY PROCEDURES .......................................... 2
RESULTS [[[ 4
SUMMARY [[[ 5
REFERENCES ................................................. 16
TABLES
1. Operational characteristics for Widows Creek Steam
Station during survey period of May 13, 1969 ............ 6
2. Physical characteristics of filter media used in
graded system ........................................... 6
3. Particle size data for air samples collected by graded
filter system from Widows Creek environs on
May 13, 1969 ............................................ 7
4. Air sampling data for samples collected at Widows Creek
Steam Station on May 13, 1969, using single filter high
volume air samplers ..................................... 8
5. Concentrations of airborne radionuclides in the environs
of the Widows Creek Steam Station operating on
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Page
7. Widows Creek Steam Station coal samples collected
during May 1969 11
8. Widows Creek Steam Station fly ash samples collected
during April - May 1969 12
9. Widows Creek Steam Station soil samples collected
during February - May 1969 13
FIGURES
1. Nested filter system 14
2. Sampling locations for Widows Creek Steam Station 15
Vlll
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ABSTRACT
Release of radioactive materials in fly ash discharged from
steam power plants burning fossil fuel, particularly coal, was
investigated. Air sampling techniques were developed to provide
useful data for use in estimating dose to critical organs, primarily
lung, in man. Procedures are described for collecting air samples
at environmental sites remote from the power plant facility.
ix
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THE AUTHORS
During the time of the work described in this report,
Dr. P. H. Bedrosian was Assistant Director for Environmental
Radiation Control at the Southeastern Radiological Health
Laboratory, Bureau of Radiological Health, Public Health Service,
U. S. Department of Health, Education, and Welfare, P. 0. Box 61,
Montgomery, Alabama 36101; he is presently assigned to Radiation
Research, Office of Research and Monitoring, Environmental Pro-
tection Agency, Rockville, Maryland 20852.
Mr. D. G. Easterly and Mr. S. L. Cummings are presently
assigned to the Eastern Environmental Radiation Laboratory,
Radiation Research, Office of Research and Monitoring, Environ-
mental Protection Agency, P. 0. Box 61, Montgomery, Alabama 36101.
* When the work described in this report was begun, this Laboratory
was part of the Department of Health, Education and Welfare, Bureau
of Radiological Health and was designated as the Southeastern
Radiological Health Laboratory, referred to herein as SERHL.
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RADIOLOGICAL SURVEY AROUND POWER PLANTS
USING FOSSIL FUEL
INTRODUCTION
The purpose of this report is to present the results of a field
study carried out in support of the Bureau of Radiological Health's
programs concerned with fossil fuel and nuclear power plants. The
field study was conducted by the Southeastern Radiological Health
Laboratory (SERHL) to gather data for assessing the public health
significance of radioactive materials discharged from fossil fuel
power plants. Field surveys focused on the discharges of fly ash
from the Widows Creek Steam Station, a coal-fired plant operated by
the Tennessee Valley Authority.
The study began in June 1966 at an oil-burning facility of the
Florida Power and Light Company at its Turkey Point site near Miami,
Florida. A previous report by Gordon^*) details this phase of the
study and the results and conclusions obtained. The survey was con-
ducted for a 26-month period and involved extensive sampling of air,
vegetation, soil, sea water, fresh water, silt and tap water from areas
on and around the site. Radionuclides such as Ra, Ra
228, 230, 232^ an
-------
The net effect of the higher radium concentrations in fly ash
and a higher fly ash discharge rate for coal plants suggested that
environmental radiation contribution would be much greater for a
coal plant than for an oil plant,and more likely therefore to be
measurable. On this basis, a survey of the H.B. Robinson plant,
a coal-fired facility at Hartsville, South Carolina, began in
December 1967. Sampling, which was not as comprehensive at this site
as it was at Turkey Point, was conducted through the cooperation of
plant and South Carolina State Health Department personnel. Analyses
of all samples, including air, soil, coal and fly ash, were made at
the SERHL. At about the same time, ancillary coal fly ash samples
were collected from the Tennessee Valley Authority's (TVA) Widows
Greek and Colbert Creek steam power plants. Over 130 air samples,
20 water samples, 60 coal and fly ash samples, and 140 silt samples
were collected from the Turkey Point, Hartsville, and TVA plant
sites during this study. More than 1400 analytical determinations
were made for all these samples. Resulting data indicated essentially
no increase in environmental levels of radionuclides in the vicinity
of the coal plant at Hartsville. In this respect, these data were as
limited as those collected from the survey of the oil plant at Turkey
Point. v=.' Because no measurable environmental distribution of fly ash
from the Hartsville plant was found, the Widows Creek coal plant which
had a lower fly ash removal efficiency, significant stack discharges,
and clearly delineated plume paths, was selected for further study.
The Widows Creek plant is located near Bridgeport, Alabama.
Operational characteristics of its eight units are listed in table 1.
On February 24, 1969, a preliminary investigation of the Widows
Creek environs was made to assess the sampling requirements and
methods needed to conduct an effective survey. Results of soil and
fly ash samples collected during this period indicated low but measurable
levels of radium in the area of the power plant. Guided by these
data, a survey of the plant environs was planned for May 13, 1969.
Air was selected as the chief environmental medium to be collected
for assessing environmental distribution of radioactive materials
discharged from the plant and for evaluating radiation dose, namely,
lung dose, to individuals in the general population.
SURVEY PROCEDURES
An air sampling technique, modified to increase collection
efficiency and to provide more useful data, was used in this survey.
Modification of the sampling technique involved the use of a nested
-------
(3)
or graded filter system v—'and the orientation of the samplers in the
fly ash plume at about 1.2 m above the ground. The nested filters
(figure 1 and table 2'—') consisted of five filters arranged in tandem,
from course to fine. This arrangement provided data characterizing
the particle sizes for use in estimating lung dose attributed to
inhalation of radioactive particles. A sampler with a single filter
was positioned alongside each nested unit for comparison purposes.
Sampling of the plume area was conducted by placing eight samplers
at sites located longitudinally and transversely on a grid along
the plume path as depicted in figure 2. Location of the air samplers
in this area was based on micrometeorological factors existing at
the time of the survey. The air sampling stations were operated
for two days, May 13 and 14, 1969. The wind remained over the grid
throughout sampling on the first day. On the second day, however, it
shifted from the grid, and air data based on samples collected
during this period were not considered usable except for station 8,
the control. Station 8 sampler operated upwind of the plant for
3 1/2 hours before it malfunctioned on the first day and ran for
31/2 hours on the second day to provide a background sample of
airborne dust. High volume samplers (1.8 m^/min) equipped with
20 cm x 22 cm sampling heads utilizing glass-fiber filters were
operated for a period of about seven hours for each station. During
this time seven of the steam plant's eight units were at approximately
95 percent capacity emitting about 32,700 pounds of fly ash per hour;
Unit 8 was shut down. Units 1 through 6 (140 MWe each) collectively
emitted fly ash at 20,700 Ibs/hr; Unit 7 (575 MWe) emitted 12,000
Ibs/hr. .These emission data were calculated from information obtained
on the Widows Creek plant and from operational data on the plant
(table 1).
Air samplers were placed at predetermined locations and in
accessible areas within the expected plume path. Portable generators
provided electricity for the high-volume blowers. Samplers and
generators were checked periodically to verify proper operation.
Sampling continued only while the plume was heading toward the
sampling area. At the end of the sampling period, each filter was
packaged in a plastic bag and shipped to the SERHL for particle size
and radioactivity determinations.
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RESULTS
Particle size determinations were performed by microscopic
analysis of the nested filters. The data for each station (table 3)
indicate that the mean diameter of practically all airborne particu-
lates sampled in the plume path ranged from 1.2 to 9 microns with little
variation noted in the particle distribution in the plume area. These
results indicate that the graded filter system was not necessary for
separating respirable particles ( < 10 microns) from nonrespirable
particles. (—)
Accurate determination of radioactivity related to the material
collected on the nested filters was not possible because of significant
interference by multiple filter background radioactivity levels. Analysis
of filters from the single system, however, proved more successful
because the radioactive particulates were concentrated on one filter. The
combined radioactivity of these particles was sufficient to be distin-
guished from filter background.
All air sampling data from the single filter system are shown in
tables 4 and 5,^ including the filter background levels for radium-226,
U-natural, thorium-232, thorium-230 and thorium-228 (table 4). These
background values were subtracted from the total filter levels to obtain
net radioactivity concentrations for calculating lung doses following
ICRP recommendations. —' Accordingly, these doses were determined by
using the general equation:
D
Pa A + Pa B
(MPC)X A (Mpc)x B
•f
L
x
where:
D = dose to critical organ (p.rem/hr)
Pa A = concentration of radionuclide A found in air (|iCi/cc)
2£
(MFC) A = maximum permissible concentration of nuclide A in air
for critical organ x (nCi/cc)
L = permitted dose rate for critical organ x. For lungs
this rate is 171 |j.rem/hr (1.5 rem/a).
Net concentrations of radionuclides in air are shown in table 5
and describe environmental contribution by the plant during the survey.
These data also support the usefulness of the air sampling techniques
used and particularly the concept of sampling air on a grid within the
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plume path. The air data reflect additional information more recent
than that previously published by Martin et al and are used to cal-
culate lune doses (table 6) which are comparable to Martin's
estimates.^—' Lung dose calculations were made on the assumption that
fly ash is insoluble in body fluids. Laboratory tests measuring the
solubility of fly ash in distilled water tend to corroborate this
assumption.
Tables 1} 8, and 9, respectively, contain summaries of analyti-
cal results for coal, fly ash and soil samples that were collected for
the Widows Creek site. These data were used in designing the field
survey and are documented to indicate environmental radiation levels.
SUMMARY
Air sampling data support the feasibility of measuring airborne
radioactive materials related to discharges from coal-burning power
plants such as the Widows Creek facility. A successful sampling pro-
cedure for collecting measurable quantities of airborne particulates
was achieved by stationing ground level air samplers at preselected
sites within the expected plume path. Resulting air data described
concentrations of radioactive materials at levels practical for use in
determining lung dose to individuals in the population. For the
Widows Creek environs, the hourly lung dose, ranging from 0.28 (j,rem
to 1.23 |j.rem, was well within the radiation guide value of 171 |j.rem/hr
for individuals in the general population.
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Table 1. Operational characteristics for Widows Creek Steam Station
during survey period of May 13, 1969
Unit #
1
2
3
4
5
6
7
8
Stack
Height (m)
51.8
51.8
51.8
51.8
82.3
82.3
152.4
152.4
Fly Ash Control
Device Efficiency (%)
Cyclone 70
70
70
70
" 70
70
Elec. ppt. 60
11 " 60
Power Rating
for 100%
Operating
Capacity (MWe)
140
140
140
140
140
140
575
570 Not
Operating
Capacity
on May 13 (%)
95
95
95
95
95
95
95
running
Table 2. Physical characteristics of filter media used in
graded system^—'
Filter Media
(downstream
order)
AAF-G 3/32
American Air
Filter Company
CM-245
Cambridge Filter
Company
#90 Dri-Pak
American Air
Filter Company
CM-285
Cambridge Filter
Company
1106 BH
Fiber Diameter
(microns)
16 ± 2
1.5 ± 0.01
Not Available
Approximate
Thickness
of Mat (cm)
0.0762
0.762
0.635
0.762
0.0356
Porosity
0.0538
0.0067
0.0023
0.0025
5.28
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Table 3. Particle size data for air samples collected by graded
filter system from Widows Creek environs on May 13, 1969
Range of CMD*
Station (microns)
1
2
3
4
5
6
7
8
*
1.7 - 7.8
2.3 - 9.0
1.7 - 6.0
1.2 - 5.8
2.3 - 8.3
2.5 - 6.8
1.5 - 5.6
Count Mean Diameter range is for
each of the five filters used at
Remarks
Filters not investigated
for particle sizing
Fifth filter in series for
Station 6, 7 and 8 not in-
vestigated for particle
sizing
mean particle size from
each station.
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8
Table 4. Air sampling data for samples collected at Widows Creek
Steam Station on May 13, 1969, using single filter high volume
air samplers.
Station Air Volume
Number (x 108cc)
1 7.0
2 7.0
3 6.7
4 5.6
5 5.8
6 4.0
7 4.9
8 7.0
Bkg concentration/
filter
(c)
Net air bkg activity
for station 8
Indicated Activity in fCi/filter(a)
226Ra 11-KB 232Th
1660±70 4600±420 190±90
1200160 3530±300 420±60
960±60 4320±400 180±40
1040±60 3710±320 350±50
1120±60 3070±260 490±70
910±60 3590±300 320±50
1060±70 25901240 260±5
750±69 27001230 240+50
750130 636133 116110
0 2060 120
(a) The error expressed is in femtocuries relative to
counting error.
230^ 228^
4201281 2341210
9401181 7471162
5801112 6361156
724H58 833H70
964H90 11181256
6481130 7241138
4201139 7911190
7361120 7521174
5401133 7031258
200 50
2-sigma
(b) Station 8, the control for this survey, was placed upwind to
measure background airborne dust.
(c) Net background activity is derived from activity
level of control
station 8 minus filter background activity.
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Table 5. Concentrations of airborne radionuclides in the environs of the
Widows Creek Steam Station operating on May 13, 1969
Station
Number
1
2
3
4
5
6
7
8
226D
Ra
1.30
0.64
0.31
0.52
0.64
0.40
0.63
0
Net
U-Nat
2.72
1.19
2.55
2.54
1.25
4.43
1.04
0
Air Concentrations*
232tt
N.D.
0.26
N.D.
0.24
0.47
0.33 x
0.12
0
23°Th
N.D.
0.29
N.D.
0.04
0.44
N.D.
N.D.
0
(fCi x 10"6/cc)
228Th
N.D.
N.D.
N.D.
0.16
0.65
N.D.
0.11
0
228Ra**
0.78
0.38
0.19
0.31
0.38
0.24
0.38
0
Net air concentration reflects subtraction of air and filter backgrounds to
obtain net contribution by plant discharge.
Radium-228 concentrations in coal fly ash were assumed to be 0.6 that of radium-226
(6.
as based on data by Eisenbud et al.
'6)
N.D. Non-detectable above filter and normal dust background.
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Table 6. Estimate of lung dose rate to individuals of general population in environs of
Widows Creek Steam Station as based on air samples collected May 13, 1969
Station
Number
1
2
3
4
5
6
7
8
(j.rem/hr
226n
Ra
0.11
0.05
0.03
0.04
0.05
0.03
0.05
0
U-Nat
0.23
0.10
0.22
0.22
0.11
0.38
0.09
0
232
J Th
N.D.
0.11
N.D.
0.10
0.20
0.14
0.05
0
23°Th
N.D.
0.17
N.D.
0.03
0.26
N.D.
N.D.
0
228Th
N.D.
N.D.
N.D.
0.14
0.54
N.D.
0.09
0
Ra
0.13
0.07
0.03
0.05
0.07
0.04
0.07
0
Total Dose
Rate
(irem/hr
0.47
0.50
0.28
0.58
1.23
0.59
0.35
0
Station 8 is the background control and therefore net values with background
subtracted would be zero.
N.D. Non-detectable.
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Table 7. Widows Creek Steam Station coal samples collected during May 1969
Sample ,,v
Identification 7, Dry1" ' % Ash
West Kentucky 91.0 13.0
East Tennessee 96.0 13.5
North Alabama 89.0 27.0
Plant Units 94.0 21.0
#1 - #6
Plant #7 87.3 16.0
Plant #7 90.6 19.0
Plant Units 93.8 16.0
#1 - #6
Indicated Activity in pCi/kg(a)
226Ra (Dry)
400±4
60±2
260±5
26017
310±6
17014
160±3
Gamma Activity
(Dry Sample)
40K 2UB1
110011010 7401330
28001950
560011010 5601290
45001990 4601290
190011050 3601320
39001980
47001990
Specific Alpha Activity
(Ash)
232
U-Nat Th
115501820 580140
65301450 510140
68801530 430140
20101200 20101100
22601190 23301200
20901180 870160
1390160 190160
(a) The error expressed is in pCi relative to 2-sigma counting error.
(b) The percent ash is based on the dry weight.
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Table 8. Widows Creek Steam Station fly ash samples
collected during April - May 1969
(b)
Identification % Dry % Ash
Widows Creek
Steam Plant 99.0 97.0
Widows Jreek
Steam Plant 96.0 96.9
Plant Units
#1 - #6 86.0 94.0
Plant Unit #7 85.8 97.0
Plant Unit #7 97.2 95.0
Plant Units
#1 - #6 98.4 92.0
Indicated Activity in pCi/kg(a)
226Ra(dry)
3330±33
1830±27
1020115
2240±25
1660±20
1130±17
Gamma Activity (Dry Sample)
144Ce
800±140
2600±490
3100±560
106n
Ru
1900*490
7201370
965±540
7901430
^Zr-95^
2001100
4°K
1650011320
1750011050
2860011720
2100011470
1910011150
2560011540
2I4Bi
48001380
41001290
18201360
28401400
30001330
16001380
Specific Alpha
activity (Ash
U-Nat
106201780
92401600
1860*170
38401370
37701350
20101200
232Th
610140
400130
17801120
18501120
14701110
20101100
(a) The error expressed is in pCi relative to 2-sigma counting error.
(b) The percent ash is based on the dry weight.
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Table 9. Widows Creek Steam Station soil samples
collected during February - May 1969
Sample (b)
Identification 7, Dry % Ash
1.6 km south-
easterly from plant 100 92
5.4 km westerly
from plant 100 93
5.4 km westerly
from plant and
beneath building 100 96
2.7 km north-
easterly from plant 100 89.9
5.9 km north-
easterly from plant 100 97
Indicated Activity in pCi/kg(a)
226,,
Ra
(Dry)
670±13
740±15
850±17
820±15
510111
Gamma Activity (Dry Sample)
144Ce
13001360
1000±380
10001320
403011050
44001840
137CS
700180
1400180
370170
28001110
25201100
106,,
Ru
11001320
10701810
14101650
95Zr-95Nb
100160
100160
340190
250170
4°K
57001680
23001620
23001580
490011180
68001950
214Bi
700120
7301260
8001180
22601590
16101450
Specific Alpha
Activity (Ash)
U-Nat
980130
1130170
1140170
10101300
1190170
232Th
880160
8501500
780110
1090160
100120
(a) The error expressed is in pCi relative to 2-sigma counting error
(b) The percent ash is based on the dry weight.
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14
AAF-G 3/32 (COARSEST)
M-245
90DW-FAK
VM-285
106 BH (FINEST)
ADAPTER FOR
8"X10" FILTERS
GASKETED HOLDER FOR FILTERS
Figure 1. Nested filter system.
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Station Distance Azimuth
Number (km) (°)
-
.
I
E
-
2.7
2.6
6.2
5.9
5.8
5.9
8.2
4.2
Map distance measured
radially from center of
plant site. Origin taken
at center of plant site
and azimuth of True North
assumed equal to 0°.
WIDOWS
CREEK
PLANT
A TVA Air Sta
O PHS Air Sta
• PHS Soil Sta
© Control
(top of 244m hill
above river)
Widows
Creek
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16
REFERENCES
1. Gordon, John A., "Interim Report of the Study of Public Health
Aspects of Fossil Fuel and Nuclear Power Plants/' Southeastern
Radiological Health Laboratory, Bureau of Radiological Health,
Public Health Service, August 1968.
2. Oakley, Donald T. and Chissler, Robert I., "Evaluation of the
Study of Public Health Aspects of Fossil Fuel and Nuclear Power
Plants," Nuclear Facilities Section, ESCP, National Center for
Radiological Health, August 12, 1968.
3. Shleien, B. et al., "Atmospheric Radioactivity Analysis and Instru-
mentation," A Status Report, NERHL-65-2, January 1965, DREW, PHS,
BRH, Northeastern Radiological Health Laboratory, Winchester,
Massachusetts.
4. Shleien, B., Cochran, J. A., and Friend, A. G., "Calibration of
Glass Fiber Filters for Particle Size Studies," American Industrial
Hygiene Association Journal, July-August 1966, 353-359.
5. Hatch, T. F. and Gross, P., Pulmonary Deposition and Retention of
Inhaled Aerosols, Academic Press, New York and London, 1964,
pp. 149-150.
6. Eisenbud, Merril and Petrow, Henry G., "Radioactivity in the
Atmospheric Effluents of Power Plants That Use Fossil Fuels,"
Science 144: 288-289 (April 17, 1964).
7. Recommendations of the International Commission on Radiological
„ Protection, ICRP Publication 2, Report of Committee II on Permis-
sible Dose for Internal Radiation (1959), Pergamon Press, New
York.
8. Martin, J. E., Harward, E. D. and Oakley, D. Te, "Comparison of
Radioactivity from Fossil Fuel and Nuclear Power Plants." Hearings
Before the Joint Committee on Atomic Energy of the United States,
First Session on Environmental Effects of Producing Electric
Power, Part 1, pp. 747-772 (1969).
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Techniques - Index
Organization for
Information Retrieva."
(C 20-8062). Copies
are available through
IBM Branch Offices.
The cards are furnished
in triplicate to allow for
flexibility in their use
(for example, author
card index, accession
number card index).
Accession No.
P. H. Bedrosian, D. G. Easterly, and
S. L. Cummings: RADIOLOGICAL SURVEY
AROUND POWER PLANTS USING FOSSIL
FUEL.
Environmental Protection Agency, Office of Research and
Monitoring, Radiation Research Publication No.EERL 71-3
(July 1970) 16 pp. (limited distribution).
ABSTRACT: Release of radioactive materials in fly ash
discharged from steam power plants burning fossil fuel,
particularly coal, was investigated. Air sampling
techniques were developed to provide useful data for use
in estimating dose to critical organs, primarily lung,
in man. Procedures are described for collecting air
samples at environmental sites remote from the power
plant facility.
(over)
P. H. Bedrosian, D. G. Easterly,, and
S. L. Cummings: RADIOLOGICAL SURVEY
AROUND POWER PLANTS USING FOSSIL
FUEL.
Environmental Protection Agency, Office of Research and
Monitoring, Radiation Research Publication No. EERL 71-3
(July 1970) 16 pp. (limited distribution).
ABSTRACT: Release of radioactive materials in fly ash
discharged from steam power plants burning fossil fuel,
particularly coal, was investigated. Air sampling
techniques were developed to provide useful data for use
in estimating dose to critical organs, primarily lung,
in man. Procedures are described for collecting air
samples at environmental sites remote from the power
plant facility.
(over)
Accession No.
Accession No.
P. H. Bedrosian, D. G. Easterly, and I
S. L. Cummings: RADIOLOGICAL SURVEfl
AROUND POWER PLANTS USING FOSSIL L
FUEL.
Environmental Protection Agency, Office of Research and
Monitoring, Radiation Research Publication No. EERL 71-3
(July 1970) 16 pp. (limited distribution).
ABSTRACT: Release of radioactive materials in fly ash
discharged from steam power plants burning fossil fuel,
particularly coal, was investigated. Air sampling
techniques were developed to provide useful data for use
in estimating dose to critical organs, primarily lung,
in man. Procedures are described for collecting air
samples at environmental sites remote from the power
plant facility.
(over)
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KEYWORDS: Radioactivity; Steam Power Plants; Power
Plant Discharges; Air Sampling; Airborne
Particulates; Fossil Fuel; Lung Dose
KEYWORDS: Radioactivity; Steam Power Plants; Power
Plant Discharges; Air Sampling; Airborne
Particulates; Fossil Fuel; Lung Dose
.-.--.
KEYWORDS: Radioactivity; Steam Power Plants; Power
Plant Discharges; Air Sampling; Airborne
Particulates; Fossil Fuel; Lung Dose
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