EMSL-LV-0539-30 EMSL-LV-0539-30
CURIUM: A BIBLIOGRAPHIC REFERENCE
Monitoring Systems Research and Development Division
Environmental Monitoring and Support Laboratory
U.S. Environmental Protection Agency
Las Vegas, Nevada 89114
May 1979
PREPARED FOR THE U.S. DEPARTMENT OF ENERGY
UNDER MEMORANDUM OF UNDERSTANDING
NO. EY-76-A-08-0539
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NOTICE
This report was prepared as an account of work sponsored by the United
States Government. Neither the United States nor the United States
Department of Energy, nor any of their employees, nor any of their
contractors, subcontractors, or their employees, makes any warranty,
expressed or implied, or assumes any legal liability or responsibility for
the accuracy, completeness or usefulness of any information, apparatus,
product or process disclosed, or represents that its use would not infringe
privately owned rights.
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EMSL-LV-0539 -30 EMSL-LV-0539 -30
CURIUM: A BIBLIOGRAPHIC REFERENCE
by
Robert E. Mosley
Monitoring Systems Research and Development Division
Environmental Monitoring and Support Laboratory
U.S. Environmental Protection Agency
Las Vegas, Nevada 89114
May 1979
PREPARED FOR THE U.S. DEPARTMENT OF ENERGY
UNDER MEMORANDUM OF UNDERSTANDING
NO. EY-76-A-08-0539
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ABSTRACT
This is a comprehensive bibliography of the literature on the element
curium that was published prior to January 1976. A short abstract is given
for each listed reference, with a few exceptions. The references are divided
into sections categorized as General, Man-Made Sources (Reactors), Man-Made
Sources (Fuel Reprocessing), Chemistry (Solubility), Chemistry (Compounds),
Chemistry (Isotopes), Analyses (Instrumental), Analyses (Chemical), Chemical
(Animal), Biological (Effects), Biological (Animal-Metabolism-Retention),
Biological (Air Movement), Biological (Human Inhalation), Measurement, and
Dosimetry. The bibliography contains author and keyword indexes and was
compiled to serve as a quick reference source for curium-related work.
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TABLE OF CONTENTS
Abstract ii
Acknowledgement iv
Citation Form v
Preface vi
Curium (Bibliographic References by Subject Category)
General 1
Man-Made Sources (Reactors) 7
Man-Made Sources (Fuel Reprocessing) 32
Chemistry (Solubility) 43
Chemistry (Compounds) 47
Chemistry (Isotopes) 55
Analyses (Instrumental) 59
Analyses (Chemical) 77
Chemical (Animal) 92
Biological (Effects) 94
Biological (Animal-Metabolism-Retention) 99
Biological (Air Movement) 108
Biological (Human Inhalation) 109
Measurement 114
Dosimetry 120
Author Index 122
Keyword Index 124
iii
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ACKNOWLEDGEMENT
The computer search of the Nuclear Science Abstracts was conducted by the
Nevada Applied Ecology Group, Oak Ridge National Laboratory. I would like to
extend my special thanks to those who participated in that search. Also
special thanks to Dr. Robert Waters, Department of Energy, Division of
Biology and Environmental Research,-Washington, D. C.
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CITATION FORM
The references are arranged by subject category. Indices are provided
for authors and key words that are located by reference number.
SAMPLE REFERENCE
1. Subject category:
2. Reference number:
3. Author:
4. Corporate author:
5. Document title:
6. Publication date:
7. Publication description:
8. Publication language:
9. KEY WORDS:
10. ABSTRACT:
11. Abstractor's initials:
Biological: Animal-Metabolism-Retention
No. 427
Makeeva, L. G.; Pavlovskaya, N. A.
Inst. of Hygiene and Preventive Medicine,
Erevan
Metabolism of Thorium Radionuclide in the
Body of Rats after Intratracheal
Introduction of a Soluble Thorium Compound
(THC14)
1973, August
Gig. Santi.; No. 8, pp. 45-47
(In Russian)
Daughter products: Intratracheal
administration: Metabolism: Radionuclide
kinetics: Rats: Thorium chlorides:
Thorium-228: Tissue distribution.
Data are presented on the rate of
resorption of thorium-228 in the blood and
the products of its dissociation. The
finding was that, after intratrachael
introduction of thorium chloride into the
body, a significant disturbance of
radioactive balance was noted to take place
in the lungs and other internal organs.
(Auth)
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PREFACE
This publication is a comprehensive bibliography on the element curium.
There is no doubt that some curium references are not included in this
bibliography but all references obtainable through a computer search of
Nuclear Science Abstracts have been included along with abstracts, with a few
exceptions. This bibliography was compiled to serve as a quick reference for
researchers evaluating curium's potential as a source of nuclear energy and
the potential threat posed by its use to man and to the environment. As a
reference source, it places at the researcher's disposal a comprehensive
listing of the existing literature on curium published prior to January 1976.
It should save much reference searching time in curium-related work.
The bibliography consists of 185 listed references that are divided into
15 categories. These categories are listed in the table of contents. With
scientific work there is always a variety of areas to be considered. By
dividing the bibliography into categories, it should be much easier to find
references that are related to the same area of interest. There are
references listed in one category that could possibly have gone in another
category, but this was unavoidable due to a certain amount of over-lapping of
the categories.
A senior author index and a keyword index have also been included for the
convenience of researchers. Both of these indexes are alphabetized with
corresponding reference numbers which are arranged in numerical order in the
bibliography.
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CURIUM: BIBLIOGRAPHIC REFERENCES BY SUBJECT CATEGORY
SUBJECT CATEGORY: General
No. 1
Bowen, V. T., and H. D. Livingston
Woods Hole Oceanographic Institute, Massachusetts
Americium-242m In Nuclear Test Debris
1975, August
Nature (London), 256(5517):482
KEY WORDS: Americium-241: Americium-242: Americium-243: Curium-242:
Environmental effects: Fallout: Fission products: Nuclear explosions:
Radiation monitoring: Seawater.
ABSTRACT: It is stated that it would be expected to find all three of
the long-lived Am nuclides, 241^ 242m/\m> ancj 243/\m> -jn ^e debris
from nuclear explosions. Weapons-grade Pu is always contaminated with
24lAm, and this nuclide has an appreciable cross section for neutron
capture leading to 242^. about 10% of such capture yields 242m/^mj the
others passing to the ground state. A small but readily measurable amount of
242cm has been found in seawater that had been contaminated by close-in
fallout from a low yield nuclear test carried out in 1962, and it is
concluded that the 242Qm observed was probably by neutron capture by
24lAm. It should be practicable to measure 242mAm -jn a variety of other
samples by searching for 242Qm supported by a longer-lived precursor. Some
interesting consequences of the measurable production of 242m/\m -jn nuciear
tests are mentioned, including environmental mobility effects. It is finally
concluded that 242m/\m wj-|i be a significant component of the debris from
future nuclear tests, or peaceful nuclear explosions, but will diminish with
increasing use of breeder reactor Pu. It is thought that a careful search
f0r 242m/\m should be made in environmental monitoring, both to establish
data on its present distribution in nature, and to establish limits on its
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influence on the environmental behavior of its descendants 242Qm ancj
238Pu. (UK)
No. 2
U.S. Environmental Protection Agency
EPA, Office of Radiation Programs, Washington, D.C.
Proceedings of Public Hearings: Plutonium and the other Transuranium
Elements
1974, December
ORP CSD-75-1, Vol. 1
KEY UORDS: Americium-241: Berkelium-249: Biological radiation effects:
Body burden: Californium-252: Cur1um-244: Diffusions: Environment:
Health hazards: Human populations: Laboratory animals: Mammals:
Neptunium-237: Personnel: Plutonium: Plutonium-238: Plutonium-2,39:
Radiation protection: Radionuclide kinetics: Radionuclide migrations:
Safety standards: Standards: Time dependence: Tissue distribution:
Transuranium elements: Uranium-233: Environmental Studies: Health and
safety: Radioactive wastes: Radiobiology: Reactor fuels.
ABSTRACT: The Environmental Protection Agency embarked on a program to
evaluate the environmental impact of the transuranium elements and to
consider whether further guidelines or standards are needed to assure
adequate protection of the general ambient environment and of the public
health from potential contamination of the environment by radionuclides of
these elements. Public hearings were held in Washington, D.C., and Denver,
Colorado, to gather information regarding the public and social implications
of plutonium utilization; the factors involved in the balancing of costs vs.
benefits; dosimetry, health, and environmental effects; environmental levels
and pathways; applications using plutonium; and control and cleanup
technology. The proceedings of the hearing in Washington, D.C., December
10-11, 1974, are presented. Data are included on current and potential
sources of transuranium elements in the environment, on animal studies on the
tissue distribution of 233Us 237Np> 238pUj 241Ani) 244Cnij 249Bk}
252Cf, and 253Es and pathological effects of body burdens of these
radionuclides, and on the health status of personnel known to have body
burdens of 238Pu or 239pu acquired during acute or chronic exposure, many
of them over 30 years previously. It is pointed out that the lack of
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demonstrable biological effects of Pu in man provides presumptive evidence
that the radiation protection standards in effect are adequate. (CH)
No. 3
Yoder, R. E., Jr.
U.S. AEC, Washington, D. C.
Potential Source Terms and Control Measures for Transuranium Elements
1974, December
Wash-1359, pp. 13-30
KEY WORDS: Californium-252: Control: Curium-244: Diffusion:
Environment: Health hazards: Human populations: Plutonium-238:
Plutonium-239: Radiation accidents: Radiation hazards: Radiation
monitoring: Radiation protection: Radioactive waste disposal: Radioactive
waste management: Radioactivity: Transuranium elements: U.S. AEC.
ABSTRACT: The current sources of transuranium materials (238pU}
239Pu> 252Cf} and 244cm) w-jthin the Atomic Energy Commission (AEC)
operations are reviewed and an indication of projected inventories and an
overview of control measures taken to reduce effluents are presented. There
have been accidental releases of Pu to the environment and these have been
well publicized. The quantities of materials involved in these instances
have ranged from much less than one to a few kilograms of material, and steps
have been taken to reduce the accident potential in AEC operations. Because
the AEC is concerned about environmental discharges and any attendant buildup
in the environment, it is fully implementing the as-low-as-practicable
concept. In those instances in which environmental cleanup actions have been
required, specific measures tailored to the situation have been used.
Because the number of the cases is very small, they are best handled on a
case-by-case basis so that a comprehensive evaluation can be made to
effectively limit the availability of these materials. (CH)
No. 4
Freeman, A. J., and D. D. Koelling
Northwestern University, Evanston, Illinois
Electronic Energy and Band Structure on the Actinide Metals
1974
Actinides: Electronic Structure and Related Properties: Vol. 1, pp. 51-108
KEY WORDS: Actinium: Americium: Band theory: Berkelium: Curium:
Electronic structure: Neptunium: Plutonium: Thorium: Uranium.
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ABSTRACT: The present state of our understanding of the electronic
properties of the actinide metals which are derived from the electronic band
theory of solids is reviewed. Energy band structure of Ac, Th, U, Np, and Pu
metals and electronic band structure of Am, Cm, and Bk are considered. (LK)
No. 5
Harrar, J. E.
California University, Lawrence Livermore Lab., Livermore, California
General Chemistry Division Quarterly Report, January-March, 1975
1975, May
UCID-15644-75-1, 33 pp.
KEY UORDS: Curium: Curium-244: Curium-245: Curium-246: Curium-248:
Einsteinium-253: Emission spectra: Uranium: Uranium-235: Uranium-238.
ABSTRACT: The status is reported for various research projects in the
Analytical Chemistry Division of the Lawrence Livermore Laboratory; including
studies on laser spectroscopy of atomic uranium, isotope shift emission
spectra of uranium and curium, and emission spectrum of einsteinium. (LK)
No. 6
Harrar, J. E.
California University, Lawrence Livermore Labs., Livermore, California
General Chemistry Division Quarterly Report, October-December 1974
1975, March
UCID-15644-74-4, 117 pp.
KEY UORDS: Berkelium: Bromine: Californium: Chlorine: Curium:
Emission spectra: Evaporation: Fluorine: Iodine: Potentiometry: Research
programs: Surface properties: Thorium: Uranium complexes: Uranium
iodides.
ABSTRACT: The status of various research projects in the Analytical
Chemistry Division of the Lawrence Livermore Laboratory is reported,
including fabrication and testing of certified subassemblies for the tritium
analyzer, emission spectra of Cm, Bk, and Cf by Fourier transform
spectroscopy; feasibility of using Ul4 as a uranium-atom source;
vaporization of U (ThD)4; atomic-beam source for cross-beam experiments
with uranium; determination of halides by potentiometric titration with
silver perchlorate; and characterization of surface properties of thorium.
(LK)
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No. 7
Argonne National Laboratory, Argonne, Illinois
Nuclear Structure and Properties and Nuclear-Atomic Interactions
1975, January
ANL-8153; pp. 18-32
KEY WORDS: Alpha decay: Einsteinium-253: Energy-level transitions:
Fermium-255: Curium-248: Energy levels: Californium-249: Single-particle
model: Strutinsky theory: Trans-104 elements: Quasi particles.
ABSTRACT: The status of theoretical and experimental studies of the
nature of residual nuclear interactions and their effect on nuclear excited
states in actinide elements is reported. Information obtained concerning
nuclear-atomic interactions is discussed. In addition, investigations of
alpha and electron capture decay, core emission in beta decay, and beta
spectrum shapes are described for several heavy elements. A new measurement
of the half-life of 233(j is included. (SDF)
No. 8
McHargue, C. J.
Oak Ridge National Laboratory, Tennessee
Metals and Ceramics Division Materials Science Annual Progress Report for
Period Ending June 30, 1975
1975, October
ORNL-5089; 68 pp.
KEY WORDS: Absorption: Alloys: Aluminum: Aluminum alloys:
Americium-241: Ceramics: Chromium: Coal: Composite materials: Copper
alloys: Corrosion: Creep: Crystal structure: Curium-244: Data
acquisition systems: Deformation: Design: Diamonds: Dielectric materials:
Diffusions: Doped materials: Eigenfunctions: Einsteinium: Electron
microscopy: Electron spin resonance: Electronic structure: Europium
compounds: Eutectics: Fabrication: Gadolinium: Gold alloys: Hafnium
alloys: Heat resisting alloys: Ion beams: Iron: Laboratory equipment:
Liquid metals: Luminescence: M codes: Magnesium oxides: Materials:
Metals: Microstructure: Monocrystals: Muffin-tin potential: Neutron
beams: Nickel-base alloys: Nickel compounds: Nickel ions: Niobium alloys:
Niobium selenides: Optical properties: Order parameters: Oxidation:
Palladium hydrides: Phase transformations: Physical properties: Physical
radiation effects: Plutonium carbides: Point defects: Precipitation
hardening: Pyrolytic carbon: Quartz: Radiation effects: Refractories:
Research programs: Scattering: Silicon carbides.
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ABSTRACT: An overview of research programs on metals and ceramics is
presented as a summary of quarterly and semiannual reports. Summaries of
research on structure of materials, deformation and mechanical properties,
transport phenomena, and radiation effects are given. (JRD)
No. 9
Hoff, R. W.
California University, Lawrence Livermore Lab, Livermore, Ca.
Excited Quasiparticle State of Odd-Mass Deformed Nuclei in the Transplutonium
Elements
1975, September
UCRL-76548; Conf-750915-8; 22 pp.
KEY UORDS: Actinide nuclei: Berkelium-249: Comparative evaluations:
Deformed nuclei: Energy levels: Even-odd nuclei: Ground states: Odd-even
nuclei: Quasi particles: Single-particle model: Transplutonium elements:
Beta-minus decay: Curium-249:
ABSTRACT: Experimental evidence is summarized from the published
literature for excited single-particle configurations in the actinide-element
deformed nuclei. Experimental data is compared for the levels of ^^Bk and
245cm with two recent theoretical treatments, one calculation of pure
single-particle and collective motions are included. In the latter half of
the paper, new information is presented on 249B|< levels from nuclear
spectroscopic measurements of 253Es alpha decay and 249Cm beta decay
performed in Lawrence Livermore Laboratory and Lawrence Berkeley Laboratory.
(5 figures) (auth)
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SUBJECT CATEGORY: Man-Made Sources (Reactors)
No. 10
Shaw, H. P.
Atlantic Richfield Hanford Company, Richland, Washington
Technical Criteria for the Prevention of Criticality
1975, February
ARH-468 (Rev. 2); p. 12
KEY WORDS: Americium-241: Americium-242: Americium-243:
Californium-244: Californium-251: Control criticality: Curium-244:
Curium-247: Fissile materials: Neptunium-237: Plutonium-238:
Plutonium-239: Plutonium-240: Plutonium-241: Uranium-233: Uranium-235.
ABSTRACT: Atlantic Richfield Hanford Company (ARHCO) Policy Guide 1.6.6,
"Criticality Prevention," and Operation Instruction 1.6.6.2, "Criticality
Prevention in Process Facilities," present the policy of the Company with
respect to the control of criticality hazards, and delegate the
responsibility of specifying safe limits for the design and operation of
process facilities to the Manager, Research and Engineering Division. The
purpose of this document is to define the technical criteria to be used in
developing the limits within which ARHCO facilities are to be designed and
operated. These criteria are based on the operating experience accumulated
from the processing of fissile materials since the year 1944. (auth)
No. 11
Crouch, E. A. C.
UKAEA Research Group, Harwell, Atomic Energy Research Establishment
Fission Product Chain Yields from Experiments in Thermal Reactors
1973, January
AERE-R-7209; 36 pp.
KEY WORDS: Fission products: Fission yield: Neutron reactions:
Standards: Tables: Caliform' um-249: Curium-245: Plutonium-239:
Plutonium-241: Thermal fission: Thermal neutrons: Thorium-227:
Thorium-229: Uranium-233: Uranium-235: Americium-241: Fission:
Neptunium-237: Pile neutrons: Protactinium-231: Thorium-232: Uranium-232.
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ABSTRACT: Published values of the yields of fission products from the
thermal-neutron-induced fission of 227Th, 229Th, 233U, 235Us 239Pu>
241pUj 242mAm, 245cm) and 2^9cf and from the "pile"-neutrons-induced
fission of 227Ac, 231Pa, 232Th, 232U, 237Np, and 241Am are accessed,
and recommended values for the chain yields are listed (16 tables, 688
references) (auth).
No. 12
Lamb, E.
Oak Ridge National Laboratory, Tennessee
ORNL Isotopic Power Fuels Quarterly Report for Period Ending September 30,
1966
1966, November; Declassified, September 1973.
ORNL-4045; 17 pp.
KEY WORDS: Alloy-TZM: Americium-241: Capsules: Cesium-137:
Compatibility: Curium oxides: Curium-242: Curium-244: Diffusion:
Fabrication: Helium: Plutonium-238: Plutonium-239: Radioisotope heat
sources: Research programs: SNAP-11 battery: Strontium oxides: Thermal
conductivity.
ABSTRACT: Properties of the curium fuel studied during this reporting
period include the rate of helium released by the decay of curium oxide and
the compatibility of two curium fuel forms with TZM. Fission-product
development consisted of the synthesis and analysis of a cesium ceramic,
determination of the thermal conductivity of SrTi03, and determination of
the thermal coefficients of expansion of SrO and SrTi03. The fabrication
of the curium fuel form, the fueling of the SNAP-11 generator, and the
simulated lunar environmental test are described, (auth)
No. 13
Lamb, E.
Oak Ridge National Laboratory, Tennessee
ORNL Isotopic Power Fuels Quarterly Report for Period Ending March 31, 1967
1967, May; declassified, September 1973.
ORNL-4131; 36 pp.
KEY UORDS: Alloy-TZM: Calorimeters: Cobalt-60: Compatibility:
Curium oxides: Curium-244: Microspheres: Molybdenum: Performance testing:
Plutonium oxides: Plutonium-238: Radioisotope batteries: Radioisotope heat
sources: Research programs: Rhenium: SNAP-11 battery: Strontium
compounds: Strontium-90: Tantalum: Tantalum alloy T-lll: Thermal
conductivity: Tungsten: Tungsten alloys.
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ABSTRACT: The fabrication and composition of compatibility couples and
test procedures for determining the compatibility of curium oxide and
candidate encapsulation materials including tantalum, T-lll, molybdenum, TZM,
tungsten and W-26% Re are detailed for 1000- and 10,000-hr exposure periods.
An apparatus for measuring the vapor pressure of curium oxide by the
transpiration method is described. The best thermocouple materials for the
244cm calorimeter was determined to be chromel-constantan when type 347
stainless steel is used as the thermal conductivity metal. Properties of
fuel form which were investigated included the thermal conductivity of
, SrTi03, and SrO pellets at different temperatures and
dissolution rates of SrO pellets in distilled water and seawater,, The heat
output of 90$r in equilibrium with 90y was determined to be 0.00686 +_
0.00023 W/curie by calorimetric measurement and radiochemical analysis of
90$rC03. The total weight requirements (source and shield) for fuel
forms of 60(;0 and 905r are compared on the basis of end-of-life power
levels for missions of 2 and 5 years. The status of sol-gel development in
the 238pu02 microsphere program is described. The thermal power of the
SNAP-11 heat source was calorimetrically measured, and the disassembly and
inspection of the SNAP-11 fuel block are reported. Welds made on Hastelloy C
capsules (to be used for the SNAP-21 generator) are illustrated, (auth)
No. 14
Lamb, E.
Oak Ridge National Laboratory, Tennessee
ORNL Isotopic Power Fuels Quarterly Report for Period Ending June 30, 1967
1967, August; declassified September 1973.
ORNL-4174
KEY WORDS: Capsules: Corrosion: Curium oxides: Curium-244: Hastelloy
C: Inconel 600: Microspheres: Oxidation: Platinum: Plutonium oxides:
Plutonium-238: Radioisotope batteries: Radioisotope heat sources: Research
programs: SNAP-11 battery: SNAP-21 battery: SNAP-7 battery: Strontium
compounds: Strontium oxides: Strontium-90: Thermal conductivity: Vapor
pressure.
ABSTRACT: The apparatus for determining the vapor pressure of curium
oxide by the transpiration method was constructed and tested. Equipment to
be used for testing inert-atmosphere systems and the operation of
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Tian-Calvert solution calorimeter are described. The minimum weight of
capsules (for the thermionic program) containing 1 kWtn of 244Cm203
and an analysis of the effects of failure criteria, length-to-diameter ratio,
and operating temperature are given. Thermal conductivity data of SrO,
Sr2Ti04, and SrTiOs were correlated and treated statistically to assess
the errors. The results show that satisfactory thermal conductivity values
can be determined using 1/2-inch-high by 1-inch-diameter uninstrumented
disks. Thermal conductivity versus temperature curves and a curve depicting
the error due to variable interface conductivity are given. The oxidation
resistance of capsule materials (Hastelloy C, Inconel 600, and platinum) in
air at 200° F and the corrosion resistance at 2000° F in clay-type soil
common in the vicinity of ORNL were determined over a period of 3 months.
The status of sol-gel development in the 238puo2 microsphere program is
given. The SNAP-7A generator was defueled and inspected, and the heat output
of the four capsules was determined and compared with the output at the start
of operation. The disassembly and inspection of the SNAP-11 fuel block was
completed. The weld development for the SNAP-21 program and the radiation
mapping of the generator assembly using a 202-W 90$K) source to simulate
the SNAP-21 fuel are described, (auth)
No. 15
Lamb, E.
Oak Ridge National Laboratory- Tennessee
ORNL Isotopic Power Fuels Quarterly Report for Period Ending December 31,
1967
1968, February; declassified September 1973
ORNL-4237: 34 pp.
KEY WORDS: Capsules: Compatibility: Curium oxides: Curium-244:
Fabrication: Hastelloy C: Haynes 25 alloy: Helium: Microspheres:
Plutonium oxides: Plutonium-238: Plutonium-239: Radioisotope batteries:
Radioisotope heat sources: Research programs: SNAP-19 battery: SNAP-21
battery: SNAP-23 battery: SNAP-7 battery: Stainless steel-304: Stainless
steel-316L: Strontium compounds: Strontium-90: Temperature dependence:
Welding.
ABSTRACT: Samples of Nd203 microspheres doped with natural boron
were irradiated to simulate helium release from 244Cm203. The
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spectrochemical determination of silicon in Cmfy was investigated
using Th02 as a stand-in for Cm02« The calorimeter for the assay of
244cm shipments was calibrated and shipped to Savannah River. Techniques
were developed for preparing and hot-pressing curium oxysulfide pellets by
using cerium as a stand-in for curium. The first set of compatibility
couples of 244(^03 and several refractory metals was fabricated and
exposed to 1650° C for 1000 hours. The welding characteristics of
superalloys for the encapsulation of ^Sr fuel were studied by using type
340 stainless steel. The weight changes of type 316 stainless steel,
Hastelloy C, and Haynes 25 specimens exposed to SrTi03 and Sr2Ti04 at
1100° C for 1000 hours were determined. The effect of thermal gradients, on
the compatibility of certain oxides was determined by using graphs of
temperature versus equilibrium partial pressure of oxygen. The oxidation
resistance of capsule materials (Hastelloy C, Inconel 600, and platinum) in
air at 2000° F and the corrosion resistance at 2000° F in clay-type soil were
obtained for periods up to 9 months. A series of tests was made to measure
the surface temperatures of a source capsule buried in a wooden box
containing soil. Microspheres of 239puQ2 were prepared by the sol-gel
process using intermediate-scale equipment in glove boxes and equipment on a
pilot-plant scale. The four disassembled SNAP-7A capsules were visually and
metallographically examined; there was no evidence of gross incompatibility
or weld defects. A temperature profile of the SNAP-23A source was calculated
assuming that the capsule was mounted in an electron-beam welder under vacuum
with vacuum gaps in the interior of the capsule, (auth)
No. 16
Lamb, E.
Oak Ridge National Laboratory, Tennessee
ORNL Isotopic Power Fuels Quarterly Report for Period Ending March 31, 1968
1968, May; declassified September 1973
ORNL-4285; 27 pp.
KEY WORDS: Capsules: Compatibility: Corrosion: Curium oxides:
Curium-244: Diffusion: Fabrication: Hastelloy C: Haynes 25 alloy: Heat
transfer: Helium: Inconel 600: Microspheres: Oxidation: Plutonium
oxides: Plutonium-238: Radioisotope batteries: Radioisotope heat sources:
Research programs: SNAP-21 battery: SNAP-23 battery: SNAP-7 battery:
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Stainless steel-316L: Strontium compounds: Strontium-90: Thermal
conductivity: Ultrasonic testing: Vapor pressure: Welded joints.
ABSTRACT: The "apparent diffusion coefficients" for
microspheres in the range of 390° C to 1200° C and for 244Cm203 pellets
in the range of 1100° C to 1400° C were determined from helium release
experiments. Samples of irradiated and unirradiated neodymium oxide
microspheres (used as a stand-in for 244Cm203 in helium release
experiments) were examined metal lographically. Five batches of curium oxide
were analyzed by the emission spectrographic technique. Equipment for the
vapor pressure measurement of curium oxides by the transpiration method was
constructed and tested. The compatibility couples of several refractory
metals exposed to 244Cm203 for 1000 hours at 1650° C were examined.
Results of compatibility tests of Haynes alloy No. 25, Hastelloy C, and
type 316 stainless steel in combination with non-radioactive SrTi03,
Sr2Ti04, and SrO for 1000 hours at 1100° C were analyzed. The thermal
conductivity of a 90$rTi03 pellet from the SNAP-7A source was measured.
The oxidation resistance of capsule materials (Hastelloy C, Inconel 600, and
platinum) in air at 2000° F and the corrosion resistance at 2000° F in
clay-type soil were obtained for periods up to 12 months. Heat transfer data
obtained by measuring the surface temperature of a source capsule buried in a
wooden box containing soil and the equation derived for predicting the
capsule surface temperature when the capsule is buried in an infinite medium
were evaluated. Equipment for studying the helium release from 2-^Pu02
was assembled and tested. The preparation of 238Pu02 microspheres by the
sol -gel process was attempted. The SNAP-21 generator was tested for 60 days.
Four welds on two fueled capsules were inspected using the ultrasonic
equipment received from Pacific Northwest Laboratory, (auth)
No. 17
Lamb, E.
Oak Ridge National Laboratory, Tennessee
ORNL Isotopic Power Fuels Quarterly Report for Period Ending September 30,
1968
1968 December; declassified September 1973
ORNL-4363; 44 pp.
KEY WORDS: Capsules: Compatibility: Creep: Curium oxides:
Curium-244: Diffusion: Fabrication: Helium: Materials testing:
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Microspheres: Plutonium oxides: Plutonium-238: Radioisotope batteries:
Radioisotope heat sources: Research programs: SNAP-21 battery: SNAP-23
battery: Strontium compounds: Strontium-90: Tantalum alloy T-lll: Thermal
conductivity: Tungsten: Ultrasonic testing: Welded joints.
ABSTRACT: Experiments have been devised to determine the rate of vapor
phase migration of 011203 encapsulated in tungsten. A compatibility
program was formulated to evaluate container materials with ^Q^OJ at
750° C and 1200° C for thermoelectric and Brayton cycle applications. A new
family of brazing alloys has been formulated as a result of the 100-hour
braze specimen aging studies at 1650° C in vacuums of 10~8 torr.
Creep-rupture testing of the tantalum alloy T-lll under varying stress and
temperature is in progress. A creep test of wrought, powder-metallurgy-
derived tungsten wire was successfully completed. The creep strength of
tungsten progressively deteriorates as oxygen pressure increases. Two
additional conceptual designs for a vented 1-kW ^^Q^QJ thermionic
test heat source have been proposed. The thermal conductivities of
90$rTi03 samples have been determined in the annealed and unannealed
conditions. Data on the leach rates continue to follow the parabolic law
within the precision of the experiments. One percent silica of
0.012-micrometer size mechanically dispersed in SrTi03 is effective in
improving the density of hot-pressed pellets. Determinations of the apparent
diffusion coefficient of helium in 238pu02 were ma(^e by measuring the
helium concentration in microspheres after steady-state helium release had
been attained. The technique for forming small-diameter (<63 micrometer)
microspheres was studied by using the normal two-fluid nozzle. The top and
bottom closure welds of SNAP-21 capsules were inspected by the pulse-echo
ultrasonic technique. Three SNAP-23 test specimens were welded with the
machined groove at the new design depth of 0.170 inch below the capsule top.
(auth)
No. 18
Lamb, E.
Oak Ridge National Laboratory, Tennessee
ORNL Isotopic Power Fuels Quarterly Report for Period Ending December 31,
1968
1969 February; declassified September 1973
ORNL-4388; 26 pp.
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KEY WORDS: Capsules: Compatibility: Creep: Curium oxides:
Curium-244: Fabrication: Hastelloy C: Haynes 25 alloy: Materials testing:
Microspheres: Plutonium oxides: Plutonium-238: Purification: Radioisotope
batteries: Radioisotope heat sources: Research programs: Rhenium alloys:
Shielding: SNAP-23 battery: Stainless steel-316L: Strontium alloys:
Strontium-90: Tungsten alloys.
ABSTRACT: Twenty-three compatibility couples for 5000- and 10,000-hour
tests at 1850° C have been completed and are ready for exposure to
temperature. Three of the group of new brazing alloys exhibited excellent
wettability on tungsten and were used in simulated capsule-to-emitter brazes.
Necessary data have been obtained to indicate the selective loss of tungsten
from the tungsten-rhenium alloy in low-pressure oxygen. The effect of
cycling the oxygen pressure between 10"^ and 10"^ torr on the creep rate
of an arc-cast-derived tungsten wire was determined. Flow parameters were
developed and used in an effort to coat 500-micrometer Th02 particles with
tantalum. Purification of ^^Cm oxides was achieved by two sequential
oxalate precipitations under closely controlled conditions of activity,
temperature, and time. Evaluation of compatibility couples of Hastelloy C,
Haynes alloy No. 25, and type 316L stainless steel with SrTi03,
SrzTiO^., and SrO continued. Experiments to measure the current total
helium inventory in the 370 and Dart I ^^PuC>2 fuels were performed.
Metallographic examination of heat-treated 238puQ2 microspheres is
underway. Ordered alloy systems are being investigated in an effort to
develop improved alloys for space applications. Creep tests on Haynes alloy
No. 25 were completed and tests to determine the creep-rupture properties
were begun. The SNAP-23 source capsule was loaded with 1127 Wtn of
90SrTi03, welded, and then loaded into the U-8% Mo shield, (auth)
No. 19
Ottinger, C. L.
Oak Ridge National Laboratory, Tennessee
ORNL Isotopic Power Fuels Quarterly Report for Period Ending March 31, 1974
1974, June
ORNL-4978; 38 pp.
KEY WORDS: Aluminum oxides: Beryllium: Capsules: Carbon: Chemical
reactions: Compatibility: Criticality: Curium oxides: Curium-244:
14
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Helium: Performance testing: Physical properties: Radioisotope heat
sources: Research programs: Thorium oxides: Zirconium oxides.
ABSTRACT: Examination of the 49 compatibility test couples which were
taken off test in December 1973 was started. Nonradioactive control couples
representative of these 49 specimens were examined. Development of the
techniques required for fabrication of the 11-couple combined compatibility/
tensile strength test matrix continued. Free energy calculations were made
covering possible reactions of 244Cm203 fuel with six potential
encapsulants. Helium release experiments at 500° C, 650° C, and 800° C were
completed. These tests indicated that the controlling mechanism for helium
release from 244^^0^ is different at different temperatures, with a
change in mechanism occurring in the region of from 600° C to 700° C. Vapor
pressure measurements were made on ^^Cm^^' A 25-W ^Q^O^ pellet
was exposed to dry air; it exhibited a similar edge-fracturing effect as that
observed in a previous test. A leach rate study was done on a sample of
air-oxidized 244(^03 fuel. Evaluation of the critical ity aspects of
three reference 244cm_fueiec| source assemblies was completed; the results
indicated that no criticality problems would be expected. A re-orientation
of the 244Qm development program from emphasis on experimental properties
measurements to emphasis on laboratory-scale developments required some
changes in the utilization of facilities and modification of some
experimental plans. Plans were initiated for a 244Qm recovery process
development experimental program, (auth)
No. 20
Ottinger, C. L.
Oak Ridge National Laboratory, Tennessee
ORNL Isotopic Power Fuels Quarterly Report for Period Ending June 30, 1974
1974, December
ORNL-5009; 39 pp.
KEY WORDS: Capsules: Compatibility: Curium oxides: Curium-244:
Emissivity: Radioactive wastes: Radioisotope heat sources: Recovery:
Research programs: Specific heat.
15
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ABSTRACT: Examination of Cm203 compatibility couples continued
with inspection of materials exposed at 900° C and at 1400° C. All of the
test materials exposed to 244Cm203 at 1400° C for 5000 hours showed some
interaction. These included both iridium and graphite, neither of which had
shown reaction at lower temperatures. Attempts to fabricate thin rectangular
pellets of 244Cm203 for use in combined compatibility/tensile strength
tests were unsuccessful, and this phase of the compatibility work was
terminated. The calculational thermodynamic reaction study phase was
completed. Total normal emittance measurements were made on a 244Cm203
pellet in the temperature range from 725° C to 1175° C. Normal spectral
emittance values were determined on the same pellet in the 3.0 to 5.0
micrometer wavelength range at three temperatures. Heat capacity measurement
work was initiated. Some nonradioactive demonstration runs of a technique
for hot pressing metal-jacketed pellets were made. Literature surveys,
calculations, and preliminary experimental work on ^^Cm recovery from fuel
reprocessing wastes continued. The first step, feed conditioning, was
investigated experimentally; and a study was performed of the applicability
of the TALSPEAK process and its modifications to the 2^^Cm recovery
problem. Design of experimental equipment was started, (auth)
No. 21
King, L. J.; J. E. Bigelow, and E. D. Collins
Oak Ridge National Laboratory, Tennessee
Transuranium Processing Plant Semiannual Report of Production, Status, and
Plans for Period Ending December 31, 1974
1975, July
ORNL-5034; 29 pp.
KEY WORDS: Americium-243: Berkelium-249: Cal ifornium-252: Curium-244:
Curium-248: Einsteinium-253: Fabrication: Fermium-257: Isotope
production: Neutron sources: Production: Research programs: Transuranium
elements.
ABSTRACT: During the period July 1, 1974, through December 31, 1974, the
following amounts of transuranium elements were recovered from 11 irradiated
HFIR targets: 1.5 g 243^ 45 g 244CrTlj 24 mg 249Bk> 252 mg 252cf}
1.25 mg 253Es, and 0.5 pg 257Fm. In addition, 34 mg of high-purity
248Cm was separated from 252Cf which had been recovered and purified
during earlier periods. Nine HFIR targets, each containing 8 to 9 g of
16
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actinides (predominantly curium), were fabricated. Some of the chemical
processing steps used for processing HFIR targets were added, deleted, or
rearranged in order to reduce processing time and increase product yields.
One cubicle equipment rack was replaced and the out-of-cell piping and
equipment associated with the remotely operated valves in the TRU cubicles
was revised. One neutron source was fabricated. Three sources that had been
used previously in various projects and returned to TRU were reloaned. A
special project was begun to recover 126$n from jpy process solutions. The
values currently in use for transuranium element decay data and for
cross-section data in planning irradiation-processing cycles, calculating
production forecasts, and assaying products are tabulated in the Appendix.
(auth)
No. 22
Delchev, Ya. I., and I. Zh Petkov.
Institute of Nuclear Research and Radiation Energy, Sofia
Nuclear Fission as a Sudden Process
1974
Compt. Rend. Acad. Bulg. Sci. (CRABA); 2^(8):1057-1059
In Russian
KEY WORDS: Californium-248: Curium-244: Half-life: Plutonium-240:
Spontaneous fission: Sudden approximation: Uranium-234
ABSTRACT: The values of log tj, were calculated for a series of
spontaneously fissioning nuclei, and the results obtained are tabulated and
compared with either experimental or previous theoretical results.
(3 Tables) (JSR)
No. 23
Pigford, T. H.
California University, Berkeley, California
Radioactivity in Plutonium, Americium, and Curium in Nuclear Reactor Fuel
1974
NP-20456; pp. VP Paper 2
KEY WORDS: Americium isotopes: Curium isotopes: Decay: FBR type
reactors: Isotope production: Nuclear fuels: Nuclear power plants:
Nuclear properties: Plutonium isotopes: Uranium.
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ABSTRACT: The following topics are discussed: formation of plutonium,
americium, and curium; radioactive decay properties; production and
utilization of plutonium in nuclear power plants; uranium-fueled light-water
reactor; light-water reactor fueled with natural uranium and recycled
plutonium; and uranium-fueled fast breeder reactor. (HLW)
No. 24
Thomas, C. W.
Battelle Pacific Northwest Labs., Richland, Washington
Radionuclides from Nuclear Power Reactors
1975, February
BNWL-1950 (Pt. 3) pp. 22-24
KEY WORDS: Americium isotopes: Carbon-14: Cesium-135: Cobalt-60:
Curium isotopes: Environment: Fission products: Forecasting: Iodine-129:
Iron-55: Manganese-54: Nickel-63: Niobium-93: Nuclear industry: Nuclear
power plants: Plutonium-238: Plutonium-239: Radioactive wastes:
Radioactivity: Samarium-151: Selenium-79: Technetium-99: Tin-126:
Tritium: Zirconium-93.
ABSTRACT: Because of the anticipated use of nuclear power reactors as a
power source, the relative concentrations of transuranium radionuclides
expected to be present in radioactive wastes from these reactors were
calculated. This will aid in predicting the environmental hazards posed by
accidental release of radioactive wastes, (auth)
No. 25
Raab, B.
Fairchild Space and Electronics Co., Germantown, Maryland
Sense II: Space Applications on Nuclear Power. Volume I. Commercial
Communications Satellite
1974, May
AEC/SNS-3063-3; 179 pp.
KEY WORDS: Comparative evaluations: Cost: Curium-244: Performance:
Plutonium-238: Power Supplies: Radioisotope heat sources: Satellites:
SNAP batteries: Solar cells: Space flight: Space vehicles: Thermoelectric
generators: Weight.
ABSTRACT: The use of nuclear radioisotope power systems for commercial
communications satellites and various military space missions, launched on
present-day booster vehicles was studied. This study was intended to provide
an evaluation of the competitiveness of radioisotope power systems as
18
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compared with solar power systems and to provide power system designers with
information on the important operating characteristics of the systems.
Curium-244 and plutonium-238 are considered as the radioisotope fuel. The
organic Rankine system, Brayton system, and thermoelectric generators were
considered as energy conversion systems. It was concluded that: the organic
Rankine cycle had a distinct weight advantage over the Brayton system;
organic Rankine and selenide-RTG-powered spacecraft are commercially superior
to state-of-the-art solar-array/battery-powered spacecraft, and potentially
competitive with the most advanced solar-array battery systems; organic
Rankine-system power permits a fully-integrated satellite configuration
resulting in a minimum weight design of optimum thermal characteristics;
selenide-RTG power permits low-weight design of superior fabrication,
integration and startup characteristics; the relative cost differences
between solar and nuclear power can be easily over-shadowed by the relative
revenue differences resulting from a net weight advantage of one of the
systems; nuclear power systems can match the flat power requirements of
commercial communications satellites without need for potentially
life-limiting batteries; and with proper design and component selection, a
curium heat source can probably be used without in-flight shielding for this
mission. (LCL)
No. 26
Atomics International Division, Canoga Park, California
Large Radioisotope Heat Source Study, Mid-Term Report to New York Operations
Office of the Atomic Energy Commission
1973, September
AI-65-144, 429 pp.
KEY WORDS: Brayton cycle: Curium-244: Plutonium-238: Polonium-210:
Power supplies: Radioisotope heat sources: Rankine cycle: Research
programs: Space vehicles: Thermoelectric generators.
ABSTRACT: The primary objective of this study was the completion of
detailed analysis and preliminary design of radioisotope heat sources which
can lead to safe, reliable power supplies on the 1- to 10-kilowatt electrical
range for various unmanned and manned space missions. The work completed by
Atomics International up to the Mid-Term Briefing (Aug. 10, 1965) is
19
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summarized. It reflects the direction being taken on such critical areas as
fuel form, capsule materials, and safety. (TFD)
No. i?7
Casagrande, R. D. and J. A. Garate
General Electric Company, Philadelphia, Pennsylvania
Design of a Curium-244 Heat Source for the Multi-Hundred-Watt Generator
1973, August
8th Intersociety Energy Conversion Engineering Conference Proceedings,
Philadelphia, Pennsylvania, pp. 117-128
KEY WORDS: Curium-244: Design: Economics: Radioisotope heat sources:
Spacecraft power supplies: Thermoelectric generators.
ABSTRACT: A preliminary design concept of a 3200 W curium-244 heat
source sized for the Multi-Hundred-Watt Radioisotope Thermoelectric Generator
is presented. The RTG utilizes 312 SiGe thermocouples, operates at a hot
junction temperature of about 1000° C, and is designed to produce 193 W(e) at
beginning of life and 125 W(e) after 5 years. The expected low cost and high
power density of the curium-244 results in very desirable reductions in
system cost and weight when compared to equivalent plutonium-238 fueled
systems. The curium RTG specific cost is estimated to be about $4,900/W and
will deliver 2.9 W/lb at beginning of life. This compares with a plutonlum
RTG specific cost of $16,000/W and a specific weight of 1.8 W/lb at beginning
of life. The RTG heat source is designed for high temperature operation,
intact reentry, and impact survival on granite at terminal velocities. A
fuel pellet geometry was selected primarily to minimize post impact heat
fluxes and because of the good existing technology for manufacture of the
sesquioxide fuel in this form, (auth)
No. 28
Carney, H. C. and N. B. Eisner.
General Atomic Company, San Diego, California
Low-Cost Ring Converter RTG
1974, June
Trans. Amer. Nucl. Soc. (TANSA); Vol. 18, pp. 9-10.
KEY WORDS: Cost: Curium-244: Cylindrical configuration: Radioisotope
batteries: Radioisotope heat sources: Thermoelectric generators
20
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ABSTRACT: From annual meeting of the American Nuclear Society;
Philadelphia, Pennsylvania (23 Jun 1974). (auth)
No. 29
Jones, I. R. and J. E. Boretz
TRW Systems, Redondo Beach, California
Design of a 400-W(e) ERTG Based on Low-Temperature Organic Rankine Cycle
Technology
1974, June
Trans. Amer. Nucl. Soc. (TANSA); Vol 18, pp. 10-11
KEY WORDS: Curium-244: Design:. Low temperature: Radioisotope heat
sources: Rankine cycle: Turbogenerators: Working fluids.
ABSTRACT: From annual meeting of American Nuclear Society; Philadelphia,
Pennsylvania (23 June 1974). (auth)
No. 30
Hansen, J. E.
Battelle Pacific Northwest Labs., Richland, Washington
Space Electric Power Program, Space Nuclear Systems Division Quarterly
Progress Report, January-March, 1969
1973, August
BNWL-1060; 58 pp.
KEY WORDS: Capsules: Chemical vapor deposition: Curium oxides:
Fabrication: Iridium: Microspheres: Oxidation: Plutonium oxides:
Plutonium-238: Polonium-210: Radioisotope heat sources: Research programs:
Rhenium: Rhodium: Spacecraft power supplies: Tantalum: Thermal
diffusivity: Tungsten.
ABSTRACT: Microballoon development studies have been completed, and a
summary of the process is presented, including economic determinations.
Rhenium microballoons were fabricated for the purpose of evaluating chemical
vapor deposition (CVD) rhenium. The CVD rhenium process was improved to a 6
to 8 p/hr deposition rate capability. Linear materials are being sputtered
onto polonide fuel surfaces, but some difficulty has been experienced in
maintaining the glove box sputtering equipment. Rare earth-polonium fueling
studies have indicated a dysprosium-polonium fuel compound which exhibits
significantly lower vapor pressure than fuel compounds obtained previously.
After special heat treatment, the fuel obtained did not release polonium
21
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between 900° C and 1200° C (>30 hours) when a surface cool enough for
polonium condensation was available. Fuel containment studies have verified
that previous test results in which polonium was released through refractory
metal claddings was due to polonium vapor, and not due to the rare earth or
other materials in the microsphere system. Fuel containment tests are in
progress for the new fuel which promise greater stability against polonium
release. Diffusion testing has indicated that at least one diffusion barrier
would be required for microsphere operation above 1000° C. Successful
oxidation protection of microspheres has been limited to 3 hours in air at
900° C. (auth)
No. 31
Killen, R. E.
Design of a Low-Weight 400-W(e) Economical Isotope Brayton System
1974, June
Trans. Amer. Nucl. Soc. (TANSA); Vol. 18, p. 10
KEY WORDS: Brayton cycle: Curium-244: Design: Performance:
Plutonium-238: Radioisotope batteries: Radioisotope heat sources:
Thermoelectric generators.
ABSTRACT: From annual meeting of the American Nuclear Society; Phil-
adelphia, Pennsylvania (23 Jun 1974). (auth)
No. 32
Distefano, J. R.
Oak Ridge National Laboratory, Tennessee
Compatibility of 244Cm203 with Containment Materials for Electric Power
Generator Systems
1975, December
ORNL-TM-4908; 60 pp.
KEY WORDS: Capsules: Compatibility: Curium oxides: Curium-244:
Graphite: Hastelloy C: Haynes 188 alloy: Haynes 25 alloy: Iridium:
Iridium alloys: Molybdenum: Molybdenum alloys: Platinum alloys:
Radioisotope batteries: Radioisotope heat sources: Rhenium alloys:
Tantalum: Tantalum alloys: Temperature dependence: Testing: Thermoelectric
generators: Thorium oxides: Titanium alloys: Tungsten alloys: Very high
temperature.
ABSTRACT: Curium-244 sesquioxide has many properties that makes it
attractive as a heat source in electric power generator systems. Current
22
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radioisotopic thermoelectric generator designs generally specify fuel-
containing interface temperatures from 800° C to 1400° C. Results of
compatibility tests of ^Q^Og with a variety of materials are
reported. Test conditions included 5000 h at 900° C and 1400° C, 2500 h at
1100° C, and static helium and dynamic vacuum environments. Materials
include graphite, TH02, superalloys, noble metals, and refractory metals.
(auth)
No. 33
Eggers, P. E. and J. L. Ridihalgh
Battelle Memorial Laboratory, Columbus, Ohio
Cost-Effective Radioisotope Thermoelectric Generator Designs Involving
244Cm and 238Pu Heat Sources
1973, August
8th Intersociety Energy Conversion Engineering Conference Proceedings,
Philadelphia, Pennsylvania, pp. 13-20.
KEY WORDS: Comparative evaluations: Curium-244: Design: Economics:
Plutonium-238: Radioisotope heat sources: Thermoelectric generators.
ABSTRACT: A comparative analysis of some of the technical considerations
surrounding the use of 244cm and 238pu heat sources in radioisotope
thermoelectric generators (RTG's) is presented. The principal considerations
in this comparative analysis include radiological shielding, ground handling,
and generator performance characteristics. The paper also describes a novel
approach to RTG design and qualification which would facilitate the use of
244Cm heat sources. This approach, which involves hermetically sealed
bellows-encapsulated thermoelectric elements, also features the potential for
increased generator output power stability and reliability and lower
converter costs accruing from the advantages of a standardized approach to
generator design, fabrication, and qualification. The results of preliminary
experimental studies involving the bellows-encapsulated thermoelectric
elements are also presented, (auth)
No. 34
Holman, R. and H. Jaspers
Westinghouse Electric Corporation, Pittsburgh, Pennsylvania.
Stirling Cycle 400-W(e) Economical Radioisotope Thermodynamic Generator
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1974, June
Trans. Amer. Nucl. Soc. (TANSA); Vol. 18, pp. 11-12
KEY WORDS: Cost: Curium-244: Performance: Radioisotope batteries:
Radioisotope heat sources: Stirling cycle: Thermoelectric generators.
ABSTRACT: From annual meeting of the American Nuclear Society;
Philadelphia, Pennsylvania (23 June 1974). (auth)
No. 35
Martin Marietta Corporation, Baltimore, Maryland
SNAP-11 Program. Final Summary Report, February 1962-January 1967
1973, September
)-2952-70-2; 319 pp.
KEY WORDS: Alloy-TZM: Capsules: Curium-242: Design: Haynes alloys:
Performance testing: Radioisotope heat sources: Research programs: SNAP-11
battery: Thermocouples: Thermoelectric generators.
ABSTRACT: A detailed summary is presented of the technical effort
performed to develop a radioisotope thermoelectric generator using a short
half-life fuel. The work was accomplished during the period from Feb. 1962
through Jan. 1967. The details of the design analysis and testing of the
various generator systems and components are presented. (LCL)
No. 36
Raab, B., A. Cherdak and D. Rusta
Fairchild Space and Electronics Company, Germantown, Maryland
Extending the Useful Life of Radioisotope Thermoelectric Generators Through
Active Power Control
1973, August
8th Intersociety Energy Conversion Engineering Conference Proceedings,
Philadelphia, Pennsylvania, pp. 31-36
KEY WORDS: Control systems: Curium-244: Electric potential: Lifetime:
Power conditioning circuits: Radioisotope batteries: Thermoelectric
generators.
ABSTRACT: The useful lifetime of a Radioisotope Thermoelectric Generator
(RTG) may be significantly extended by use of a "mobile-shunt" power
conditioning system in preference to the more common shunt-dissipative type.
A mobile-shunt regulator has been designed which automatically performs this
function, as well as producing a regulated stepped-up DC voltage for the
24
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load. The mobile-shunt regulator is expected to be particularly useful for
generators fueled with curium-244. This potentially low-cost fuel has a
half-life of 18.1 years, thus requiring some 20% excess fuel at
beginning-of-1ife in order to achieve missions of 5 years. This could well
result in excessive high beginning-of-1ife hot junction temperatures and high
material degradation rates which would prevent the achievement of the
required end-of-mission power. The use of a mobile shunt in place of a shunt
regulator for a curium-244 silicon-germanium RTG can increase operating
lifetime by 20- to 50-percent for a given operating temperature range,
depending upon the efficiency of the mobile-shunt system, (auth)
No. 37
Osmeyer, W. E.
Teledyne Isotopes, Timonium, Maryland
Economic Modular RTG Systems
1974, June
Trans. Amer. Nucl. Soc. (TANSA); Vol. 18, pp. 6-7
KEY WORDS: Cost: Curium-244: Design: Radioisotope batteries:
Radioisotope heat sources: Thermoelectric generators.
ABSTRACT: From annual meeting of the American Nuclear Society;
Philadelphia, Pennsylvania (23 June 1974). (auth)
No. 38
Schumann, F. A. and W. J. Barnett
Teledyne Isotopes, Timonium, Maryland
Cost Effective Designing for the Economic RTG
1974, August
9th Intersociety Energy Conversion Engineering Conference Proceedings,
San Francisco, California. CONF-740805, pp. 204-208
KEY WORDS: Curium-244: Design: Economics: Optimization:
Plutonium-238: Power supplies: Radioisotope heat sources: Space vehicles:
Spacecraft power supplies: Thermoelectric generators.
ABSTRACT: The Economic Radioisotope Thermoelectric generator to be
fueled with 244Qm or 238pu for generation of 400 W(e) after 5 years of
unattended mission operation is being developed. The approach taken to
optimize the cost is described. (TFD)
25
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No. 39
Erdmann, R. C., E. C. Gritton, and M. J. Ozeroff
Rand Corporation, Santa Monica, California
Some Characteristics of Radioisotope Power Sources in an Ocean Environment
1974, March
AD/A-002129; P-5056-1; 33 pp.
KEY UORDS: Cobalt-60: Curium-244: Electronic equipment: Polonium-210:
Radioisotope heat sources: Seas: Shielding: Thermoelectric generators:
Underwater.
ABSTRACT: The results of the study show that lightweight radioisotope
heat sources can be considered for use undersea with little shielding
necessary for electronic packages in close proximity to the heat source.
Acceptable integrated electronic dose levels of 10^ rads for gamma
irradiation and 10,000 reps for neutron bombardment were obtained for
extended mission times for the three isotopes considered. It is unnecessary
to shield the isotope 210p0 for electronic protection. However, use would
be restricted because of its short half-life and this isotope could present
special heat management problems not encountered with either ^Co of
244Cm. For 244Cm and 60Co it was found that the shield around the
electronic package becomes important due to the strong backscattering effect
of neutrons and gammas from the surrounding seawater. The 244Qm neat;
source appears to require less shielding to electronics level and would
therefore take up less volume in the undersea system than the 60Co heat
source. (GRA)
No. 40
Liberman, A. R. and W. E. Osmeyer
Teledyne Isotopes, Timonium, Maryland
10% Efficient Economic RTG Design
1974, August
9th Intersociety Energy Conversion Engineering Conference Proceedings;
San Francisco, California. CONF-740805, pp. 197-203
KEY WORDS: Curium-244: Design: Performance testing: Plutonium-238:
Power supplies: Radioisotope batteries: Radioisotope heat sources: Space
vehicles: Spacecraft power supplies: Thermoelectric generators.
ABSTRACT: A new RTG design study has resulted in a modular reference
design for a nominal 400 W(e) end-of-mission (EOM) 244Cm-fueled Economic
26
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Radioisotope Thermoelectric Generator (ERTG). The ERTG exhibits
beginning-of-life (BOL) specific power of over 11 W per kg and fits an
envelope 0.20 x 0.92 x 1.53 meters. The modular construction of the ERTG
allows convenient selection of unit power levels from 80 to 800 W, in 80 W
increments, with only minor changes to the housing length and configuration.
The ERTG reference design, its predicted performance, and key related
information on the selenide thermoelectrics and copper-water heat pipes are
discussed, (auth)
No. 41
Aller, P. F. and R. J. Miskuff
Teledyne Isotopes, Timonium, Maryland
Modular Heat Source for 244Cm and 238Pu
1974, August
9th Intersociety Energy Conversion Engineering Conference Proceedings;
San Francisco, California. CONF-740805, pp. 147-151
KEY WORDS: Curium-244: Design: Plutonium-238: Power supplies:
Radioisotope heat sources: Space vehicles: Spacecraft power supplies:
Thermoelectric generators.
ABSTRACT: A radioisotope heat source is presented to satisfy the
following: (1) provide a significant improvement over state-of-the-art heat
source performance; (2) be optimally integrable with a thermoelectric
converter; (3) contain either 244Cm or 238Pu fuel; (4) be adaptable to a
large range of power levels with little or no modifications; and (5) meet
newly established safety criteria. The design approach consisted first of
itemizing all known requirements or desirable characteristics and
categorizing them. All existing heat source technologies were examined and
evaluated in detail with respect to the parameters desired for this heat
source. The design characteristics and safety attributes were then used to
generate a number of heat source designs. The considerations examined
included shapes, materials, capsule construction, insulation techniques,
vents, number of heat sources, arrangement of heat sources, isolation from
thermopile, and shielding. The following analyses were applied: (1) safety:
the important parameters being probability of failure due to launch pad abort
(blast, fire, and impact), probability of failure due to reentry melting of
27
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capsule or excessive thermal stresses in heat shield, probability of failure
due to impact, burial, and post impact oxidation, recovery probability of
capsules after reentry and impact, and overall hazards per individual unit;
(2) reliability; (3) cost; (4) weight; and (5) integration, with important
characteristics such as venting, interchangeableity of fuel (244Cm or
238Pu), facility of fueling, and modularity (growth potential). The design
approach followed and its utilization for optimum design selection is
described. The final heat source design is described and its performance,
both nominal and during probable abort conditions, is discussed. The heat
source, as characterized, is compared with other state-of-the-art heat
sources, (auth)
No. 42
Teledyne Isotopes, Energy Systems Division, Timonium, Maryland
Economic Radioisotope Thermoelectric Generator Study Program. Cost
Effectiveness Study
1973, November
IESD-3112-4; 57 pp.
KEY WORDS: Communications: Curium-244: Design: Economics:
Plutonium-238: Power supplies: Satellites: Thermoelectric generators.
ABSTRACT: The recently completed economic radioisotope thermoelectric
generator (ERTG) study, (IESD-3112-1) and its resulting design definition
were greatly dependent on a parallel cost-effectiveness study and the results
of numerous cost trade-offs. Both the total program activity and the ERTG
design have been cost optimized. (TFD)
No. 43
Teledyne Isotopes, Energy Systems Division, Timonium, Maryland
Economic Radioisotope Thermoelectric Generator Study Program. Program Plan
1973, November
IESD-3112-3; 149 pp.
KEY WORDS: Communications: Curium-244: Design: Planning:
Plutonium-238: Power suppl ies: Satellites: Thermoelectric generators.
ABSTRACT: This program plan describes the effort required to develop,
test, and manufacture the 400 W(e) economic radioisotope thermoelectric
generator (ERTG) for space applications. The initial program is described in
IESD-3112-1. (TFD)
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No. 44
Teledyne Isotopes, Energy System Division, Timonium, Maryland
Economic Radioisotope Thermoelectric Generator Study Program. Final
Technical Report
1973, October
IESD-3112-1; 216 pp.
KEY WORDS: Communications: Curium-244: Design: Plutonium-238: Power
Supplies: Satellites: Thermoelectric generators.
ABSTRACT: This study was initiated April 2, 1973 to evaluate various
radioisotope thermoelectric generator concepts and select a reference design
which would provide a safe, reliable, economic 400 W(e) power supply for use
in future space communication satellites. Nine basic concepts and 18
additional trade-off configurations were evaluated during the study program.
The reference design ERTG is a generator with 400 W(e) EOM (5.5y) output, 15
standard heat source blocks, an improved all-selenide thermopile, and two
heat pipe augmented fins for waste heat rejections. The generator uses
244Cm as fuel but will accept 238Pu. (TFD)
No. 45
Teledyne Isotopes, Energy Systems Division, Timonium, Maryland
Economic Radioisotope Thermoelectric Generator Study Program. Appendices,,
Final Technical Report
1973, October
IESD-3112-2; 350 pp.
KEY WORDS: Communications: Curium-244: Design: Performance:
Plutonium-238: Power supplies: Satellites: Thermoelectric generators.
ABSTRACT: This report consists of 14 appendices to the economic
radioisotope thermoelectric generator (ERTG) study program described in
IESD-3112-1. The appendices are entitled: Concept Summary Sheets; Low
Temperature Heat Pipe Technology: Selenide T/E Technology and Test Data;
Improved TAGS/2N T/E Technology; Bimetallic Seal Technology; Cold End
Hardware Technology; Thermal Insulation Technology; Thermal Control
Technology; Nuclear Safety Criteria; Heat Source Selection and
Compatibility; Heat Source Response Analysis; Search and Recovery; Shield
Analysis - Methods and Models; and Heat Pipe Attachment Techniques. (TFD)
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No. 46
Williams, E. W. and R. C. Howard
National Aeronautics & Space Admin., Moffett Field, California
Preliminary Designs for 100-Watt (e) Isotope Thermionic Electrical Power
Modules
1967, November
Proceedings of the Thermionic Conversion Specialists Conference, CONF-671149;
TID-24229, pp. 32-41
KEY WORDS: Curium-244: Design: Polonium-210: Power range 10-100 W:
Radioisotope batteries: Spacecraft power supplies: Thermionic converters.
ABSTRACT: Preliminary designs are presented for 100 W(e) isotope
thermionic electrical power modules employing curium-244 and polonium-210 as
isotope fuels. The modules are to be used as basic power units, which in
multiples, can supply spacecraft electrical power requirements in the 0.5 to
2 kW range. Module design criteria are outlined, design descriptions
presented, and performance estimates summarized, (auth)
No. 47
Harbour, R. M., D. E. Troutner, and K. W. MacMurdo
Savannah River Laboratory, E. I. du Pont de Nemours and Company, Aiken, S.C,
Nuclear Charge Distribution in Fission: Fractional Independent Yield of
135Xe from Thermal-Neutron-Induced Fission of 245Cm and 249Cf
1974, August
Phys, Rev. C. (PRVCA); 10_(2): 769-773.
KEY WORDS: Californium-249: Curium-245: Fission yield: Neutron
reactions: Thermal fission: Thermal neutrons: Uranium-233: Xenon-135.
ABSTRACT: Target foils containing 245Cm or 249Cf prepared by
electrodeposition on high-purity aluminium foils were irradiated in a
Savannah River Plant production reactor operated in a high flux mode. The
135Xe activity was measured for each foil as a function of time-after-
irradiation by counting the 249.6-keV Y-ray emission with a 45-cm3 Ge(Li)
detector. From these measurements, the fraction of the A = 135 mass chain
produced directly as 135Xe relative to the total production of 135I plus
135Xe was calculated. The measured fractional independent yield of 135Xe
from 245Cm fission is 0.17 ± 0.02, and from 249Cf fission is 0.36 ± 0.03.
These yields are compared with those of 135Xe from thermal-neutron-induced
fission of 233U, 235U, 239Pu, and 241Pu. (auth)
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No. 48
Mosley, W. C., Jr., and P. K. Smith
U.S. Atomic Energy Commission
Freeze Drying Method for Preparing Radiation Source Material
1975, March
PAT-APPL-252,643; 6 pp. U.S. Patent 3,873,651 to U.S. Atomic Energy
Commission.
KEY WORDS: Actinium-227: Americium-241: Americium-243:
Californium-252: Cobalt-60: Curium-242: Curium-244: Drying: Fabrication:
Freezing: Plutonium-238: Polonium-210: Radiation sources.
ABSTRACT: A solution containing radioisotope and palladium values is
atomized into an air flow entering a cryogenically cooled chamber where the
solution is deposited on the chamber walls as a thin layer of frozen
material. The solvent portion of the frozen material is sublimated into a
cold trap by elevating the temperature within the chamber while withdrawing
solvent vapors. The residual crystals are heated to provide a uniformly
mixed powder of palladium metal and a refractory radioisotope compound. The
powder is thereafter consolidated into a pellet and further shaped into rod,
wire or sheet form for easy apportionment into individual radiation sources.
(auth)
No. 49
Oak Ridge National Laboratory, Tennessee
Transuranium-Element Processing
1975, October
ORNL-5050; pp. 20-23
KEY WORDS: Americium-243: Berkelium-249: Californium-252: Curium-244:
Einsteinium-253: Fabrication: Fermium-257: Isotope Production: Neutron
Sources: Production: Transuranium elements.
ABSTRACT: Two target processing campaigns were conducted, and 23 HFIR
targets were processed. Key isotopes in the campaign products are
244Cm, 259Bk, 252Cf, 253Es, and 257Fm. Five sources containing
from 0.9 to 13yg 252Cf were fabricated. (LK)
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SUBJECT CATEGORY: Man-Made Sources (Fuel Reprocessing)
No. 50
Brown, P- E., E. Lamb, and D. G. Albertson
General Electric Company, Philadelphia, Pennsylvania
Availability and Cost of Curium-244 from Power Reactor Fuel Reprocessing
Wastes
1973, August
8th Intersociety Energy Conversion Engineering Conference Proceedings;
Philadelphia, Pennsylvania, pp. 129-142
KEY WORDS: Availability: Cost: Curium-244: Fabrication: Production:
Radioisotope heat sources: Recovery: Reprocessing: Spacecraft Power
supplies.
ABSTRACT: As a compact source of thermal energy, the radioisotope
curium-244 has the advantages of high specific power, 2.8 W(t)-g~1 (pure
244Cm), and long half-life, 18.12 years. The practical application of
244Cm for the generation of electrical power in space depends on its
availability and cost to the user. The operation of a nuclear/electric power
generating station will yield 244Cm as the product of six successive
neutron captures in the uranium-238 which is the preponderant constituent of
the nuclear reactor fuel. Projections of curium availability from the wastes
generated in the reprocessing of typical LWR fuel cores through the General
Electric Company - Midwest Fuel Recovery Plant and from other sources are
given. The sensitivity of curium production to the level of fuel burnup and
the effect on the quantity of curium produced, if piutoniurn-enriched uranium
fuels are used is discussed. Based on the projected availability and the
possible chemical flow sheets, probable costs for the recovery of raw 244Cm
are developed. To be useful in a heat source, 244Cm must be available in
chemical and physical forms that are well characterized. The problems
associated with the fabrication and encapsulation of fuel in heat sources are
examined. The status of curium isotopic fuel form development and heat
source technology is reviewed. The probable costs of 244Cm in a qualified
heat source are derived from consideration of fuel form and heat source
fabrication requirements, (auth)
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No. 51
Carney, H. C., J. J. Shefcik, Jr., and H. H. Van Tuyl
General Atomic Company, San Diego, California
Curium-244 Recovery from Spent Reactor Fuel
1974, June '
Trans. Amer. Nucl. Soc.; Vol. 18, 13 pp.
KEY WORDS: Availability: Barnwell fuel processing plant: Cost:
Curium-244: Isotope production: Liquid wastes: Power reactors:
Reprocessing: Separation processes: Spent fuels.
ABSTRACT: From annual meeting of the American Nuclear Society;
Philadelphia, Pennsylvania (23 June 1974).
No. 52
Eberle, S. H. and W. Robel
Kernforschungsanlage Juelich G.M.B.H. (F. R. Germany)
Determination of the Formation Rate and the Purity of Transuranium Elements
1973, October
Jul-11 (Bd.2), pp. 3-18. AED-Conf-73-702-006.
KEY WORDS: Capture: Cross sections: Isotope production: Neutron
reactions: Nuclear reaction yield: Self-Absorption: Alpha spectra:
Americium-243: Americium-244: Curium-244: Americium-241: Americium-242:
Cardiac pacemakers: Curium-242: Impurities: Neutron emission: Oxygen-18:
Plutonium-236: Plutonium-238: Purification.
ABSTRACT: The transuranium nuclides Np-237, Am-243, and Cm-244 are
formed in large amounts in the nuclear reactor and can be isolated from the
waste of nuclear fuel reprocessing. Their use as highly valuable sources of
energy or radiation cannot, however, be covered on a long-term basis by the
reprocessing of waste alone; consequently, a directed synthesis of especially
the neutron reactions or resulting products to be obtained from the above
nuclides must be considered. Thus the microscopic neutron capture cross-
sections of Np-237, Am-241, Am-243, Cf-252 and Es-253 were determined and the
yield of the nuclides produced. Np-238, Cm-242, Cm-244, Es-253, Fm-254 (the
last four are e-transition products of the first produced Am-242, Am-244,
Cf-253, and Es-254) were determined by gamma and alpha spectroscopy. The
presently important Pu-238 can be obtained by irradiation of Np-237 as well
as of Am-241. Its use as a cardiac pacemaker requires extreme purity.
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Special processes have been worked out to test the purity. Amongst these are
the determination of the Pu-236 content, that of the neutron emission rate
and that of the 0-18 content and measures for the improvement of the degree
of purity. (GE)
No. 53
Finsterwalder, L.
Gesellschaft Zur Wiederaufarbeitung Von Kernbrennstoffen MBH, Karlsruhe, Ger.
Space and Exhaust Gas Monitoring in Reprocessing Plants or Other Large
Technical Installations
1974, March
KFK-1899; pp. 147-151. In German.
KEY UORDS: Air: Americium: Cesium-134: Cesium-137: Curium: Fuel
processing plants: Gaseous wastes: German Federal Republic: Krypton-85:
Off-Gas systems: Plutonium: Radiation monitoring: Radiation protection:
Radioactive wastes: Radioactivity: Strontium-90: Tritium.
ABSTRACT: The system used at the Karlsruhe fuel reprocessing plant (WAK)
for monitoring internal air, exhaust air, and off gases is described.
Following an explanation of the measuring principles used, operating
experience is reported and suggestions are given for future installations.
(tr-auth)
No. 54
Girardi, F., and G. Bertozzi
Commission of the European Communities, Ispra (Italy). Joint Research Centre
Long-Term Alpha-Hazard of High Activity Waste from Nuclear Fuel Reprocessing
1974, December
EUR-5241E; 31 pp.
KEY UORDS: Americium: Curium: Environment: Neptunium: Plutonium:
Radiation hazards: Radioactive waste storage: Reprocessing: Safety: Spent
fuels: Stability: Underground disposal: Uranium.
ABSTRACT: The concentration and decay of a-emitters in high activity
waste arising from spent nuclear fuel reprocessing was calculated under
specified reference conditions. An attempt to evaluate the long-term hazard
is being made by applying the "barrier" approach derived from reactor safety
studies. Four barriers were identified which could be evaluated in a
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probabilistic way by taking into account the great uncertainties present in
each of them. The barriers are: (1) quality of the segregation afforded by
deep geological formations, (2) stability of conditioned waste (chemical and
physical), (3) retention by immediate surroundings, and (4) distribution
pattern of actinides in the environment. Chemical separation of actinides
from high activity waste would be an additional option of undoubted value for
the disposal of high activity waste. An analysis of various levels of
possible separations suggests that a reasonable target might be: Pu, Am, and
Cm, decontamination factor 103; Np, coextraction with U and Pu with a 90%
yield, (auth)
No. 55
Gourisse, D.
Cen, Fontenay-Aux-Roses, France
By-Product Recovery in the Reprocessing of Nuclear Fuels
1973, October
Bull. Inform. Sci. Tech. (Paris) No. 185, pp. 5-29. In French.
KEY WORDS: Americium: Americium-241: Americium-243: Bibliographies:
Cerium: Cerium-144: Cesium: Cesium-137: Curium: Curium-242: Curium-244:
Isotope production: Neptunium: Neptunium-237: Promethium: Promethium-147:
Reprocessing: Solvent extraction: Spent fuels: Strontium: Strontium-90.
ABSTRACT: Some transuranic elements (237Np, 241Am, 243Am, 242Cm,
and 244Cm) and fission products (137Cs, 90Sr, 144Ce and 147Pm)
appear as useful by-products in the reprocessing of nuclear fuels. Recovery
processes are reviewed. Particular emphasis is given to large-scale
processes, especially to solvent extraction based methods. Processes
developed in France are outlined and situated in the international context.
(FR)
No. 56
McElroy, J. L.
Battelle Pacific Northwest Labs., Richland, Washington
Research and Development Activities Waste Fixation Program. Quarterly
Progress Report April-June 1975
1975, September
BNWL-1932; 96 pp.
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KEY WORDS: Aluminum oxides: Calcination: Cesium: Chrdmium oxides:
Curium: Fault Tree Analysis: Fluidized Bed: Glass: Leaching: Liquid
Wastes: Melting: Radioactive waste disposal: Radioactive Waste processing:
Research programs: Ruthenium: Safety: Solidification: Vitrification.
ABSTRACT: Four engineering-scale in-canister melting tests established
melting rates in 8- and 12-in-diameter canisters and investigated feed-rate
limitations resulting from the use of in-canister fins. The ceramic melter
was fed glass frit, calcine and frit powder, concentrated slurry, and liquid
waste with powdered frits. Comparative leach tests demonstrated that the
reference waste glass has higher leach resistance than many common minerals.
A test program was completed which-shows the pressurization potential of
calcines stored in sealed canisters and subjected to high temperatures.
Tests were made of glass samples to measure the radiation damage. Long-term
compatibility of certain refractory oxides in molten glass was studied to
select improved refractories for joule-heated melters. Glass samples doped
with curium were examined to assess radiation damage and to determine helium
diffusion coefficients. Vaporization behavior of glass and calcine samples
at elevated temperature was investigated to evaluate storage and shipping
accident conditions. Several methods of coating calcine particles were
tested for alternative waste fixation. Retention of cesium and ruthenium in
supercalcines was studied. The computer code system for providing ordered
lists of the highest risk sequences from among the myriad failure sequences
associated with large fault trees was successfully demonstrated. (LK)
No. 57
Hittman Associates, Inc., Baltimore, Maryland
Study of the Economics and Consequences of Recovery of Radioisotope Fuel
Forms from Space Systems
1973, September
SC-DC-65-1677; 61 pp.
KEY WORDS: Curium-244: Economics: Plutonium-238: Polonium-210:
Promethium-147: Radioisotope batteries: Radioisotope heat sources:
Recovery: Spacecraft power supplies: Thermoelectric generators.
ABSTRACT: The recovery of radioisotope fuel from space power systems
from the standpoint of economics is evaluated. In addition, the effect of
recovery on fuel production and availability is considered. The isotopes
considered include 238Pu, 210Po, 147Pm, and 244Cm. (TFD)
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No. 58
Shevchenko, V. B., V. S. Smelov, A. G. Kozlov, V. V. Chubukov, V. P. Lanin,
and E. Ya Smetanin
Extraction of Americium, Curium, Strontium, and Rare-Earth Elements from
Residual Aqueous Solutions Obtained in Reprocessing Spent Fuel Elements of
Water-Moderated Water-Cooled Power Reactors
1974, November
At. Enrg. (USSR); 37_(5):379-383. In Russian.
KEY WORDS: Americium: Aqueous solutions: Curium: Phosphoric acid:
Esters: Rare earths: Reprocessing: Solvent extraction: Spent fuels:
Strontium.
ABSTRACT: Conditions providing quantitative extraction of strontium,
americium, curium, and rare-earth elements from an aqueous solution are
examined theoretically along with the regimes of fractional separation of
these elements in re-extraction operations using diethyl phosphoric acid.
The successful practical application of the devised regimes is illustrated by
the extraction and separation of strontium, americium, curium, and rare-earth
elements from residual aqueous solutions obtained in regenerating spent fuel
elements of water-moderated water-cooled power reactors, (auth)
No. 59
Wheelwright, E. J., L. A. Bray, H. H. Van Tuyl, and H. T. Fullam.
Battelle Pacific Northwest Labs., Richland, Washington
Flowsheet for Recovery of Curium From Power Reactor Fuel Reprocessing Plant
Waste
1974, May
BNWL-1831; 109 pp.
KEY WORDS: Americium: Barnwell fuel processing plant: Curium:
Curium-244: Flowsheets: Ion exchange: Isotope production: Liquid wastes:
Neptunium: Plutonium: Radioactive waste processing: Separation processes:
Solvent extraction: Uranium.
ABSTRACT: Curium-244 has the potential of providing an inexpensive
source of power for radioisotope thermoelectric generators. Flowsheets for
the recovery of curium from spent-power-reactor fuels were studied and two
selected flowsheets were recommended for further development. The flowsheets
were designed to process all of the high-level liquid waste from the Barnwell
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Nuclear Fuel Plant (5 tonnes of fuel per day) with the waste being aged 3
years before processing. Recovery of at least 80% of the curium was desired
with a product purity of over 97%. Flowsheets were evaluated with respect to
technical feasibility, time of curium availability, relative cost, and impact
on waste management. A secondary objective was to include neptunium recovery
in the flowsheet. Two flowsheets are described which merit continued
development work: (1) a reference flowsheet consisting of solvent-extraction
and ion-exchange steps, and (2) an improved flowsheet using only solvent
extraction, but based on incomplete laboratory data. The reference flowsheet
consists of the following steps: (1) feed clarification by centrifugation,
(2) removal of Pu, Np, and U by solvent extraction, (3) acid destruction by
reaction with sugar, (4) a second clarification by centrifugation, (5)
purification by ion exchange, and (6) waste disposal. The principal
advantage of the reference flowsheet is that little additional process
development is required, so that early curium availability is possible, while
the principal disadvantage is the adverse impact on waste management. The
improved flowsheet consists of the same operations for the first four steps,
followed by a solvent-extraction process to separate curium from the rare
earths, other fission products, and process reagents. A final separation of
curium from americium might require a small-scan ion-exchange operation.
This flowsheet has the advantages of low cost and minimum impact on wastes,
but has the disadvantage of longer lead time before curium availability.
Each flowsheet is compatible with a neptunium recovery process demonstrated
at the Hanford Purex Plant. Effluent from Step 2 (Pu, Np, U removal) is
concentrated, neptunium is further concentrated by solvent extraction, and
purified by ion exchange. Additional research and development work is
recommended on each of the two curium flowsheets so that options can be kept
open for either early recovery of curium or recovery of curium at lowest
cost, (auth)
No. 60
Oak Ridge National Laboratory, Tennessee
Separations Chemistry Research and Development
1975, October
ORNL-5050; pp. 27-35
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KEY WORDS: Americium: Aromatics: Chemical reaction kinetics: Curium:
HDEHP: Leaching: Neptunium: Nitric acid: Plutonium: Pyrazoles: Radium:
Rare earths: Reduction: Reprocessing: Separation processes: Solvent
extraction: Spent fuels: Stability: Uranium ores.
ABSTRACT: Acylated pyrazolones in mixture with donor additions, such as
TOPO and TBP, were examined as selective extractants for plutonium and the
transplutonium actinides from acidic reprocessing waste solutions.
Bifunctional phosphonates have potential applicability to separating
americium, curium, and rare earths from all of the other fission products in
fuel reprocessing wastes without prior destruction of the HN03. In the
project to investigate the leaching characteristics of radium from uranium
ores and sulfate-leached ore tailings, a study was made of the interrelation
of the effective solubilities of calcium, strontium, barium, and radium
sulfates. An improved flowsheet was devised for removal of americium and
curium from reprocessing wastes. Since plutonium will be recovered from
spent reactor fuels by the Purex, in which Pu(IV) is extracted into TBP from
HN03 feed solution, experiments were designed to determine the stability of
Pu(IV) in HN03 and in synthetic fission product solutions at various
temperatures and acidities of interest. A study of the kinetics of the
reduction of Np(IV) to Np(VI) in nitric acid solution by ferrous nitrate was
made using spectrophotometric methods. (LK)
No. 61
Bond, W. D., and R. E. Leuze
Oak Ridge National Labs., Tennessee
Removal of Actinides from High-Level Wastes Generated in the Reprocessing of
Commercial Fuels
1975, September
Conf-750913-9, 21 pp.
KEY WORDS: Americium: Curium: Fuel reprocessing plants: Liquid
wastes: Neptunium: Plutonium: Purex Process: Radioactive Waste
Processing: Radioactive wastes: Reprocessing: Separation processes:
Solvent extraction: Spent fuels: Uranium.
ABSTRACT: Progress is reported on a technical feasibility study of
removing the very long-lived actinides (uranium, neptunium, plutonium,
americium, and curium) from high-level wastes generated in commercial
reprocessing of spent nuclear fuels. The study was directed primarily at
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wastes from the reprocessing of light water reactor (LWR) fuels and
specifically to developing satisfactory methods for reducing the actinide
content of these wastes to values that would make 1000-year-decayed waste
comparable in radiological toxicity to natural uranium ore deposits.
Although studies are not complete, results thus far indicate the most
promising concept for actinide removal includes both improved recovery of
actinides in conventional fuel reprocessing and secondary processing of the
high-level wastes. Secondary processing will be necessary for the removal of
americium and curium and perhaps some residual plutonium. Laboratory-scale
studies of separations methods that appear most promising are reported and
conceptual flowsheets are discussed, (auth)
No. 62
Claiborne, H. C.
Oak Ridge National Labs., Tennessee
Effect of Actinide Removal on the Long-Term Hazard of High-Level Waste
1975, January
ORNL-TM-4724; 48 pp.
KEY WORDS: Americium: Curium: Fission products: HTGR type reactors:
Neptunium: Plutonium: Protactinium: Radiation hazards: Radioactive waste
disposal: Radioactive waste management: Radioactive waste processing:
Thorium: Uranium: Water-Cooled reactors.
ABSTRACT: A possible method for improving the management of high-level
radioactive waste involves the removal of actinides to a very high degree to
reduce the long-term hazard potential of wastes stored in geological
formations. In this method, actinides are removed to levels where their
contribution to the hazard potential is comparable to that from the
long-lived fission products. Removal of actinides to this extent reduces the
long-term (>1000 years) hazard potential of high-level waste to about 5% of
that for pitchblende mineral on the basis of the hazard index. Calculations
showing removals of 99.99% plutonium, 99.9% uranium, americium, and curium,
and 95% neptunium from spent uranium-plutonium fuels accomplish this result.
(auth)
No. 63
Godbee, H. W., J. G. Moore, A. H. Kibbey, and D. S. Joy
Oak Ridge National Labs., Tennessee
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Leach Behavior of Cementitious Grouts Incorporating Radioactive Wastes
1975, May
CONF-750535-1; 42 pp.
KEY WORDS: Cesium-137: Curium-244: Leaching: Liquid wastes: Mortars:
Plutonium-239: Radioactive waste processing: Radioactive waste storage:
Solidification: Strontium-85.
ABSTRACT: Grouts similar to those used in the Hydrofracture Facility at
Oak Ridge National Laboratory (ORNL) were made by blending simulated
intermediate-level waste solution containing ^Sr, 137QS$ 239pUj or
244cm with a dry mixture of cementitious materials and selected clays, and
the products tested for retention of these isotopes in International Atomic
Energy Agency (IAEA)-type leach tests. The fraction of isotope leached
varied with the square root of time if leachate replacement was more frequent
than once a day, but was inhibited or depressed if changed less often. When
Grundite clay (for cesium retention) was present, the isotope leach rates
followed the order: Cs greater than Sr greater than Cm greater than Pu, with
overall results indicating that grouts can give leach rates comparable to
those obtained for wastes incorporated into borosilicate glasses. Curing a
grout specimen up to 28 days in humid air before leaching decrease the amount
leached from the specimen. The leach rate for cesium was decreased by the
addition of Grundite, pottery clay, or Conasauga shale. These additives, as
listed, are in the order of increasing effectiveness with respect to cesium
retention. Theoretical relationships that consider diffusion and
instantaneous reaction (an equilibrium or time-independent relationship
between mobile and immobile forms of a species) give good agreement with the
data for the 28-day-cured grouts when the lechate was initially replaced
twice per day. Using the derived modified effective diffusivities, De,s;
comparisons were made of the amounts leached from a 55-gal drum of grout
assuming two different forms for the drum, a semi-infinite medium and a
finite cylinder. These calculations show that the drum approximates a
semi-finite medium for a few years if the De is approximately 1 x 10"9
cm^/sec and for more than 3000 years if the De is approximately 6 x
10~18 cm^/sec. They also show that the projected amounts leached from a
waste product which is assumed to approximate semi-infinite medium are
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conservative (on the side of safety) since they are equal to or greater than
the amounts predicted by a solution based on the actual geometry of the
finite product, (auth)
No. 64
Oak Ridge National Labs., Tennessee
Waste Management
1975, October
ORNL-5050; pp. 4-19
KEY WORDS: Americium: Curium: Fuel cycle: Geologic deposits:
Leaching: Liquid wastes: ORNL: Radioactive waste disposal: Radioactive
waste processing: Radioactive wastes: Reprocessing: Salt deposits:
Separation processes: Spent fuels: Transmutation.
ABSTRACT: Status of the following studies is reported: Geologic
Disposal Evaluation Program: Processing modifications for improved waste
management; leaching of radionuclides from waste solids; methods for
management of ORNL liquid wastes; and projections of radioactive wastes from
the nuclear fuel cycle. (LK)
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SUBJECT CATEGORY: Chemistry (Solubility)
No. 65
Myasoedov, B. F., I. A. Lebedev, V. M. Mikhailov, and V. Ya Frenkel
Inst. of Geochemistry and Analytical Chemistry, Moscow
Possibility of the Oxidation of Cm(III) and Pr(III) to the Tetravalent State
in Aqueous Solutions
1974, June
Radiochem. Radioanal. Lett.; r7_(5-6) :359-365
KEY WORDS: Aqueous solutions: Curium: Curium-244: Nitric acid:
Oxidation: Ozone: Phosphoric acid: Potassium carbonates: Praseodymium.
ABSTRACT: Anodic oxidation of Pr(III) in 8M HN03 and 15M H3P04, as
well as oxidation by ozone in 10M HIM^, 15M H3P04 and 50% 1(30)3
solutions does not yield Pr(IV). On the other hand, introduction of a large
amount of 244^ into a 15M ^04 solution does not hinder the
electrochemical oxidation of Am(III) and slightly decreases the stability of
Am(IV) having been formed. These results indicate that the electrochemical
oxidation of Cm(III) in 15M ^04 does not occur owing to the great redox
potential of Cm(IV)-Cm(III) couple and not because of radiolysis. (auth)
No. 66
Korotkin, Yu. S.
Moscow
Hydrolysis of Transuranium Elements. II. Hydrolysis of Americium(III) and
Curium(III) in Pure Nitric Acid Solutions
1973
Sov- Radiochem; 15.(5) :682-685
KEY WORDS: Americium: Americium compounds: Cations: Cerium: Chemical
reaction kinetics: Chromatography: Curium compounds: Hydrolysis: Nitric
acid.
ABSTRACT: An investigation was made of the mechanism of the hydrolysis
of Am and Cm in pure HN03 solutions up to pH _<5.5. The addition of Li+
and NH4+ ions to the HN03 suppresses hydrolysis and shifts the
equilibrium toward the formation of nitrate complexes at pH <2. At low pH
values (>4) the same operations produce the reverse effect, (auth)
43
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No. 67
Korotkin, Yu. S.
Moscow
Hydrolysis of Transuranium Elements. V. Hydrolysis of Americium and Curium
in Perchloric Acid Solutions
1974
Sov. Radiochem.; 16(2):223-226
KEY WORDS: Americium: Curium: Hydrolysis: Perchloric acid:
Polymerization.
ABSTRACT: A study was made of the hydrolysis of americium and curium at
concentrations of 10~6 - 10~4 M in 'perchloric acid solutions. The
presence of several sorptionally heterogeneous forms with different charges
may be explained by the formation of outer-sphere hydroxyl groups by
hydrolysis of hydrated americium and curium ions. It was observed that the
polymerization of hydrolysis forms of americium and curium begins with a
concentration of them of 10~4 M. (auth)
No. 68
War'd, J. W., R. W. Ohse, and B. Reul
Europaishes Institut Fur Transurane, Karlsruhe, Federal Republic of Germany
The Vapor Pressure of High-Purity Solid and Liquid Curium
1975, March
J. Chem. Phys.; 62(6):2366-2372
KEY UORDS: Curium-244: Entropy: Fusion heat: Liquid metals:
Molecular beams: Vapor pressure: Very high temperature.
ABSTRACT: The vapor pressure of triply distilled curium-244 metal has
been measured in the temperature range 1300-2000°K, using Knudsen effusion
target-collection techniques. Precise geometrical conditions were chosen to
insure that the intercepted molecular beam came entirely from the curium
sample surface within the cell. Second-law equations are Logiop (atm) =
(6.082 ± 0.129) - (19,618 ± 193)/T (K) (solid 1327-1639 (K), Log10P (atm) =
(5.586 ± 0.157) (18,894 ± 275)/T (K) (liquid, 1640-1972 (K). From these
data, the heat and entropy of fusion transition are calculated to be 3.31 cal
and 2.19 cal/deg, respectively. The average second-law entropy is 25.56 ±
0.72 cal/deg. Similarities noted in other work between the chemical and
physical properties of curium and gadolinium were clearly evident. (3rd-law)
44
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= 92,128 ± 76 cal for the heat of sublimation from the solid phase, 92,482 ±
112 cal for the liquid. Difficulties encountered in high-temperature
effusion studies with reactive materials are discussed in the light of these
and earlier results, (auth)
No. 69
Korotkin, Yu. S.
Gesellschaft Fuer Schwerionenforschung F. R. Germany
Preparaton of Cyclotron Targets from Transplutonium and Rare Earth Elements
by Electrolytic Deposition from Isobutanol
1974, February
GSI-tr-74 5, 20 pp. In German.
KEY WORDS: Butanols: Chemical preparation: Chemical reaction kinetics:
Curium isotopes: Electric currents: Electric potential: Electrodeposition:
Electrodes: Electrolysis: Ethanol: Gadolinium: Ion beams: Irradiation:
Layers: Quantity ratio: Radioactivity: Rare earths: Samarium: Stability:
Targets: Titanium: Transplutonium elements: Ytterbium.
ABSTRACT: The process of electrolytic deposition of transplutonium
elements and rare earth elements from isobutanol was investigated, leading to
the definition of process conditions allowing the preparation of cyclotron
targets up to 2 mg/cm^ which are'resistant to irradiation with accelerated,
multiply charged neon or oxygen ions. Small additions of ethanol (1 to 5%)
will induce the formation of gas during the electrolytic deposition of the
transplutonium and rare earth elements. (GE)
No. 70
Chiarizia, R., P- R. Danesi, M. A. Raieh, and G. Scibona
Cnen, Casaccia, Italy
Liquid Ion Exchange Selectivity of Dinonylnaphthalene-sulfonic Acid (HD) with
Respect to Some Lanthanide and Actinide Ions
1975, June
J. Inorg. Nucl. Chem.; 37(6):1495-1501
KEY WORDS: Americium: Americium compounds: Californium: Californium
compounds: Cations: Cerium: Cerium compounds: Curium: Curium compounds:
Dielectric properties: Europium: Europium compounds: Gadolinium:
Gadolinium compounds: Ion exchange: Organic solvents: Partition:
Perchloric acid: Sulfonic acid esters: Thulium: Thulium compounds.
45
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ABSTRACT: The liquid ion exchange selectivity of dinonylnaphthalene-
sulfonic acid (HD) dissolved in a series of organic diluents covering the
dielectric constant range 2.38 to 34.8 with respect to the cations Ce3+,
Eu3+, Gd3+, Tm3+, Am3+, Cm3+, Cf3+ in perchloric solutions has
been studied at 25° C. The extent of aggregation of HD in the different
diluents and the equilibrium constants of the exchange reactions have been
evaluated. As far as the dependence of the ion exchange selectivity on the
diluent nature is concerned, a decrease of the selectivity with the increase
of the diluent dielectric constant has been evidenced only in the case of
M3+ -H+ exchange. The reasons for-this behavior are discussed together
with literature data concerning other liquid ion exchange systems, (auth)
No. 71
David, F.
Paris University, Orsay, France
Redox Potentials and Electronic Structure of 4F and 5F Elements
1973
Rev. Chim. Miner.; _10(4) :565-576
KEY WORDS: Actinium: Americium: Berkelium: Curium: Electronic
structure: Enthalpy: Neptunium: Oxidation: Plutonium: Protactinium:
Rare earths: Redox potential: Thorium: Uranium.
ABSTRACT: The redox properties of 4f and 5f elements are compared and
discussed. The variation in free redox enthalpy with degree of oxidation
occurs as with d elements: linear function when ions of the same electron
configuration are considered. In contrast, the stability variations of the
state of oxidation with Z for 91 < Z < 103 elements demonstrate the existence
of a distinct series of elements behaving very differently from d elements.
(PR)
46
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SUBJECT CATEGORY: Chemistry (Compounds)
No. 72
Zachariasen, W. H.
Los Alamos Scientific Lab., New Mexico
Bond Lengths and Bond Strengths in Compounds of the 5F Elements
1975
Conf-750913-6; 6 pp.
KEY WORDS: Actinium bromides: Actinium chlorides: Actinium compounds:
Actinium fluorides: Actinium oxides: Americium bromides: Americium
chlorides: Americum compounds: Americium fluorides: Americium oxides:
Berkelium bromides: Berkelium chlorides: Berkelium compounds: Berkelium
fluorides: Berkelium oxides: Binding energy: Bond lengths: Californium
bromides: Cal iform'urn chlorides: Californium compounds: Californium
fluorides: Californium oxides: Chemical bonds: Curium bromides: Curium
chlorides: Curium compounds: Curium fluorides.
ABSTRACT: The variation of bond length (D) with bond strength (S) in
normal valence compounds of 3d, 4d, 5d-4f, and 6d-5f elements can be
represented approximately D(S) equals D(0.5) F(S), where D(0.5) is a
characteristic constant for a given bond and F(S) an empirical function which
is the same for all bonds. A bond strength S-jj equals Sjj is assigned to
the bond between atoms i and j such that SIGMAj S-jj equals v-j and
SIGMA-j S-jj equals Vj, where v-j and Vj are the normal valences of
the two atoms. The function F(S) decreases monotonically with increasing S,
and is normalized to unity at S equals 0.5, so that the constant 0(0.5) has
the physical meaning of being the bond length adjusted to S equals 0.5. The
method described above was used to interpret and systematize the experimental
results on bond lengths in oxides, halides, and oxyhalides of the 5f
elements, (auth)
No. 73
Tret'yakov, Yu. 0.
Moscow
Chemistry of Non-stoichiometric Oxides
Izdatel'stvo Moskovskogo Universiteta; 364 pp.
47
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KEY WORDS: Beryllium oxides: Cerium oxides: Chemical composition:
Chemical reaction kinetics: Chemistry: Crystals: Curium oxides:
Dysprosium oxides: Electrical properties: Electrolytes: Erbium oxides:
Europium oxides: Ferrites: Ferroelectric materials: Gadolinium oxides:
Hafnium oxides: Holmium oxides: Lanthanum oxides: Lutetium oxides:
Magnetic properties: Mechanical properties: Metals: Molybdenum oxides:
Neodymium oxides: Niobium oxides: Oxides: Piezoelectricity: Plutonium
oxides: Praseodymium oxides: Promethium oxides: Samarium oxides: Scandium
oxides: Sintering: Solids: Terbium oxides: Thermodynamic properties:
Thorium oxides: Thulium oxides: Tungsten oxides: Uranium oxides: Vanadium
oxides: Ytterbium oxides: Yttrium oxides: Zirconium oxides.
ABSTRACT: Many properties of oxygen-containing inorganic materials
(ferrites, piezoelectric crystals, ferroelectric crystals, solid
electrolytes, and bioceramics) are clearly related to their nonstoichiometric
composition. The current theories on the nature of the nonstoichiometric
defects in simple and complex oxides are examined. The methods and results
of the study of nonstoichiometry in important systems of the metal-oxygen
type are described. Special attention is given to a thermodynamic analysis
of disordering processing in oxide crystals. The effect of nonstoichiometry
on the kinetics and mechanisms of solid-state reactions, including sintering,
and on the chemical, magnetic, electrical, and mechanical properties of the
oxides and ferrites is examined. Among the oxide systems discussed are those
of V, Y, Zr, Nb, Mo, the rare earths, Hf, W, Th, U, Pu, Cm, Be, and Sc.
(Tr-auth)
No. 74
Stevenson, J. N.
Tennessee University, Knoxville, Tennessee
Microchemical Preparations of Metallic Curium-248 and Californium-249 by the
Reduction of Their Trifluorides, and Related Structural Studies
1973
University Microfilms Order No. 84-11, 292 pp.
KEY UORDS: Berkelium-249: Californium-249: Chemical preparation:
Curium-248: FCC lattices: HCP lattices: Curium Nitrides.
ABSTRACT: Samples of the trifluorides of californium-249, curium-248 and
curium-244 were prepared. The high temperature, trigonal modification of
CfF3 was prepared by quenching methods and the phase transitions were
studied. The average, room-temperature lattice parameters determined for the
trigonal structure are: a0 = 6.945 (3)A; c0 = 7.101(2)A. Previously
48
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unreported values for orthorhombic CfFs were averaged with reported values
to obtain room-temperature lattice parameters of: ag = 6.653(3)A; b0 =
7.039(1)A; eg = 4.393(2)A. The transition temperature was estimated to be
between 550° C and 700° C. The average, room-temperature lattice parameters
for 248cmF3 are: a0 = 7.014(3)A; CQ = 7.194(3)A; and for 244CmF3
they are ag = 7.019(18)A; eg = 7.198(20)A. The average parameters
determined from the radiation-damaged 244CmF3 samples were not
significantly different from those of 248CmF3. The accuracy of the
lattice parameters determined for 244CmF3 does not justify a definitive
statement on the presence or absence of radiation-induced expansion of the
244CmF3 lattice. Experimental apparatus and methods were developed for
the microchemical preparations of metallic curium-248,, berkelium-249, and
californium-249 by the reduction of the trifluorides at elevated
temperatures. The same apparatus and methods were used to prepare metal
samples ranging in size from below 10 mg up to 500 mg and with volatilities
covering several orders of magnitude. Curium-248 metal was found to exhibit
the face-centered cubic (fee) and double hexagonal closet-packed (dhcp)
phases analogous to those of curium-244 metal. Average, room-temperature
lattice parameters for the dhcp phase of curium-248 metal are: ag =
3.500(3)A; eg = 11.34(1)A; and for the fee phase: a0 = 5.070(8)A. For
the first time the complete reversibility of the transformation between the
phases has been demonstrated, thus supporting the conclusion that the fee
phase is a true, high-temperature form of curium metal. Californium-249
metal was found to exhibit a fee structure with an average, room-temperature
lattice parameter ag = 4.994(12)A. The possibility of the existence of
other phases was indicated by the presence of additional lines in one
pattern. The nitrides of curium-248 and berkelium-249 were prepared by
reaction of the metals and or their hydrides with nitrogen. Curium-248
nitride was found to exhibit a fee structure with an average,
room-temperature lattice parameter ag = 5.027(12)A. One sample of
berkelium nitride yielded the fee parameter ag = 5.010(4)A. The reported
error limits on the average values of lattice parameters represent the 95%
confidence level calculated by using the standard statistical method for the
average of independent determinations. The error limits (2 a] reported for
49
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the lattice parameter of BkN indicates only the internal consistency of that
set of data. (Diss. Abstr. Int., B)
No. 75
Stepanov, A. V.
Russia
Electromigration Method for the Study of the Kinetics of the Complex
Formation of Eu(III), Am(III), and Cm(III) with 1,2-diamine-cyclohexane-
tetra-acetic Acid.
1974
Kompleksoobrazovanie I Ekstraktsiya Aktinoibov I Lantanoidov, pp. 55-60
KEY WORDS: Americium compounds: Chemical reaction kinetics: Chemical
reactions: Curium compounds: DCTA: Electrophoresis: Europium compounds:
Medium temperature.
ABSTRACT: The rate constants for the reactions of formation and
dissociation of complexes of Am(III), Eu(III) and Cm(III) with DCTA were
studied in the pH range from 2.3 to 2.9 at m = 0.1 (KN03 medium) using the
electromigration method in non-equilibrium conditions. The rate of the
direct reaction obeyed a second order equation with the values kgi = (3.6 +_
0.3) x 107, (3.6 ±0.3) x 107 and (3.0 +0.3) x 107 1/mol sec for Am,
Eu, and Cm at 25° C. The dissociation reactions also obeyed a second order
kinetic equation. The values of kg2 at 25° C were equal to 4.4 +_0.03, 3.2
+_ 0.3, and 2.6 +_ 0.2 1/mol sec for Am, Eu, and Cm. From the temperature
dependence of kgi and kQ2 the activation parameters were determined for
the direct and reverse reactions, (tr-auth)
No. 76
Elesin, A. A., and A. A. Zaitsev
Russia
Some Regularities During the Complex Formation of Am(III)
1975
Kompleksoobrazovanie I Ekstraktsiya Aktinoibov I Lantanoidov, pp. 49-54
KEY WORDS: Americium complexes: Carboxylic acids: Chemical
preparation: Chemical reaction kinetics: Curium complexes: Organic
phosphorus compounds: Promethium complexes.
ABSTRACT: Regularities during the complex formation of Am(III), Cm(III)
and Pm(III) with some phosphorus- and carboxyl-containing ligands were
50
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examined. The correlation dependences were established and explanations were
given for the deviations observed, (tr-auth)
No. 77
Tsameryan, I. I., D. S. Gol'dshtein, and E. I. Atamanova
Russia
Decontaminability of Certain Paints Containing 237Np, 241Am, 242Cm and
244Cm
1974, November
At. Energ. (AENGA); 37_(5):390-392
KEY WORDS: Acetic acid: Americium-241: Curium-242: Curium-244:
Decontamination: Neptunium-237: Organic chlorine compounds: Paints:
Permanganates: Polyethylenes: PVC: Removal: Resins: Sodium carbonates:
Sodium fluorides: Surface cleaning.
ABSTRACT: The decontaminability of certain paints based on resin SVH-40,
mixtures of post-chlorinated poly(vinyl chloride) and alkyd resins,
pentaphthalic resin PFL-64, and chlorosulfurized polyethylene containing
237Np, 24l/\m, and 242>244Cm was studied. Samples of paints applied to
metallic plates were contaminated with IN nitrate solution of all the
indicated isotopes and also with nitrate solutions of 24^Am and 242»244Cm
at pH~3. The samples were decontaminated at first with a solution
containing 5% Na2C03 + 0.1% KMn04 + 0.4% (NaPOsJs and then with 0.3
N H2C204 + 0.2% NaF + 0.5% of the detergent "Novost". A "contamination-
washing" cycle was repeated five times. The highest decontaminability of 10
tested paints was found in HS-76 lacquer (CVH-40 resin solution in a mixture
of organic solvents). Neptunium is significantly more difficult to remove
from paints than americium and curium, especially from paints based on epoxy
resins. The decontaminability of certain paints decreases with increasing
acidity of contaminating solutions. Lacquer HS-76 is recommended as an outer
layer of protective coating when working with Np, Am and Cm. Its initial
contamination can be reduced by decontamination as much as 500 to 1,000
times, (auth)
No. 78
Damien, D., J. P. Charvillat, and W. Muller
Cea-Cen, Fontenay-Aux-Roses, France
Preparation and Lattice Parameters of Curium Sulfides and Selenides
1975, July
Inorg. Nucl. Chem. Lett.; lit7'8):451-457
51
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KEY WORDS: Chemical Preparation: Crystal Lattices: Crystal structure:
Curium selenides: Curium sulfides: Lattice parameters: Oxygen compounds:
X-Ray diffraction.
ABSTRACT: The preparation and x-ray characterization of curium sulfides
and selenides is described. Substoichiometric disulfide and diselenide
crystallize in the tetragonal system, presumably of Fe2As type.
Body-centered cubic sesquisulfide and sesquiselenide exhibit the defect
Th3P4 structure type. Curium oxysulfide Cn^S is isostructural with
hexagonal plutonium oxysulfide. (auth)
No. 79
Nugent, L. J.
Oak Ridge National Labs., Tennessee
Standard Electrode Potentials and Enthalpies of Formation of Some Lanthanide
and Actinide Aquo-Ions
1975, July
I. Inorg. Nucl. Chem.; 37_(7-8) :1767-1770
KEY WORDS: Actinium compounds: Americium compounds: Aqueous solutions:
Berkellum compounds: Californium compounds: Cations: Cerium compounds:
Curium compounds: Einsteinium compounds: Electric potential: Electrodes:
Europium compounds: Fermi urn compounds: Formation heat: Gadolinium
compounds: Hoi mi urn compounds: Lanthanum compounds: Lutetium compounds:
Polarography: Samarium compounds: Terbium compounds: Uranium compounds:
Water: Ytterbium compounds.
ABSTRACT: Polarographic first half-wave amalgamation potentials for many
of the lanthanide and actinide aquo-ions M(III) aq were reanalyzed according
to recent interpretations of the amalgamation mechanisms. The analysis
yields new values for some of the standard electrode potentials E^M(O-III)
and E°M (O-II) and the standard enthalpy of formation H M(III) aq. The
lanthanide metals La, Ce, Sm, Eu, Gd, Tb, Ho, Yb, and Lu, and the actinide
metals Ac, U, Am, Cm, Bk, Cf, Es and Fm are treated, (auth)
No. 80
Lougheed, R., and E. K. Hulet
Lawrence Livermore Lab., California University, Livermore, California
Preparation of Thin Actinide Targets for the Synthesis of the Transactinide
Elements
1974, October
UCRL-75782; Conf-741043-3; 8 pp.
52
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KEY WORDS: Californium fluorides: Curium fluorides: Curium-248:
Curium-249: Deposition: Isotope production: Sublimation: Targets:
Transplutonium elements.
ABSTRACT: The sublimation method proved to be a valuable new procedure
for preparing thick, adherent actinide targets having a high chemical purity.
Deposition yields are acceptable, especially since the charge material is
easily recoverable. Observation of the deposits on different metal
substrates, the ESCA data, and free energy calculations indicate that the
very good adherence to Be and Al substrates may be due to a surface reaction
of the actinide fluoride with the metal substrate to form a thin layer of
actinide metal or an intermetallic between the substrate and the deposited
fluoride. Physical and chemical analyses of these sublimed deposits are
being continued, (auth)
No. 81
Charkin, 0. P-
Inst. of New Chemical Problems, Moscow
Valence States of Atoms and Stability of Principles of Gaseous Compounds of F
Elements
1974
Zh. Strukt, Khimi; !L5_(6):985-992
KEY WORDS: Actinium: Americium: Berkelium: Californium: Cerium:
Curium: Dysprosium: Einsteinium: Electrons: Erbium: Europium:
Excitation: Gadolinium: Hafnium: Holmium: Lanthanum: Lutetium:
Neodymium: Neptunium: Plutonium: Praseodymium: Promethium: Protactinium:
Samarium: Terbium: Thorium: Thulium: Uranium: Valence: Ytterbium.
ABSTRACT: The principles of the variation of the energies of atomization
of compounds of the rare earth elements as a function of the period, the
position of the f element in the period, and of its valence are discussed
within the framework of the model described earlier. The conclusions of the
model are in good correlation with the experimental data, (auth)
No. 82
Charvillat, J. P-, U. Benedict, D. Damien, and W. Muller
CEA, Fontenay Aux Roses, France
Preparation and Lattice Parameters of Some Americium and Curium Pnictides
1975, March
Radiochem. Radioanal. Letti.; 20_(6): 371-381
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KEY WORDS: Americiutn compounds: Americium phosphides: Antimony
compounds: Chemical preparation: Crystal structure: Curium arsenides:
Curium compounds: Curium phosphides: Lattice parameters.
ABSTRACT: The preparation and x-ray characterization of some americium
and curium pnictides are described. The previously unknown compounds AmP,
CmP, CmSb, CmAs were found to exhibit the NaCi type of structure, and
Am4$b3 to crystallize in the body-centered structure of
type, (auth)
No. 83
Martinet, L., J. Reul, and G. Duyckaerts
University Liege
Chronopotentiometric Study of the Reduction of Trivalent Curium in Molten
(Li-K)Cl Eutectic
1975, April
Anal. Lett.; £(4):233-239
KEY WORDS: Cations: Curium: Curium compounds: Eutectics: High
temperature: Lithium chlorides: Molten salts: Potassium chlorides:
Reduction.
ABSTRACT: A Chronopotentiometric study of the reduction Cm(III) +
3e—Cm(0) is reported. The diffusion coefficient increases from 3.6 x
10~6 cm^ sec"-'- to 17.2 x 10"^ cm^ sec ~1 in the temperature range
400° C to 500° C. Diffusion data of various +1, +2, +3, and +4 ions are
compared with regard to the charge density of the ions, (auth)
No. 84
Pasto, A. E.
U.S. Energy Research and Development Administration
Method of Forming High Density Oxide Pellets by Hot Pressing at 50° C to
100° C above the Cubic to Monoclinic Phase Transformation Temperature
1975, August
Pat-Appl-359,397 pp.
KEY WORDS: Actinide compounds: Curium oxides: Europium oxides:
Fabrication: Fuel pellets: Gadolinium oxides: Hot pressing: Oxides:
Powders: Promethium oxides: Rare earth compounds: Samarium oxides: Very
high temperature.
ABSTRACT: A process for low temperature sintering of rare earth and
actinide oxides which have a cubic to monoclinic transformation is described,
The process involves hot pressing a powder compact at a temperature just
above the transformation temperature, (auth)
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SUBJECT CATEGORY: Chemistry (Isotopes)
No. 85
Erskine, J. R.; G. Kyle, R. R. Chasman, and A. M. Friedman
University of Minnesota, Minneapolis; Argonne National Laboratory, Argonne,
Illinois
Study of 249Bk, 241Am and 231Pa with Proton Transfer Reactions
1975, February
Phys. Rev., C.; 11(2)1561-579
KEY WORDS: Differential cross sections: Energy spectra: Excitation
functions: MeV range 10-100; One-Nucleon transfer reactions: Stripping:
Angular distribution: Berkelium-249: Curium-248: Deuterons: Helium-3
reactions: Tritons.
ABSTRACT: Proton single-particle states have been studied in the
isotopes 249Bk, 241Am, and 231Pa. The reaction (a,t) was utilized in
the three studies. Additionally, the reaction (3He, d) was used in the
study of levels in 249Bk. Many new levels were observed, and some could be
interpreted in terms of single-particle orbitals. Also, several assignments
previously made on the basis of radioactive decay studies were confirmed by
the orbital signatures seen in the proton transfer spectra. Single-particle
energies are extracted from the experimental data. Deformations of the
nuclear central potential are deduced for 249Bk and 241Am. By use of the
parameters of the central field for 249Bk, the fy/2 - fs/2 splitting is
deduced for mass 250 at zero deformation and estimated for mass 300. (auth)
No. 86
Hooshyar, M. A., and F. B. Malik
Arya-Meher Univ. of Tech., Teheren
Total Spontaneous Fission Half-Lives, Kinetic Energy, and Mass Yield Spectra
of 250Cm, 245Cf, and 2%m
Helv. Phys. Actai; 46(5):724-728
KEY WORDS: Californium-245: Curium-250: Fermium-258: Fission
fragments: Fission yield: Half-Life: Kinetic energy: Mass number:
Spontaneous fission.
ABSTRACT: The absolute spontaneous fission half-lives of 250Cm,
254Cf, and 258Fm, the preference of 258Fm to decay in symmetric modes
55
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and trends of half-lives of even curium and californium isotopes are
accounted for within the context of a theory of fission using an interaction
characterized by a thin external barrier, (auth)
No. 87
Yamaji, S., A. Iwamoto, S. Suekane, and K. Harada
Institute of Physical and Chemical Research, Japan
Mass Asymmetry in the Fission of Actinide Nuclei
1974, December
NP-20480(P8); PP. 113-117
KEY WORDS: Californium isotope's: Curium isotopes: Fermi urn isotopes:
Fission barrier: Fission fragments: Mass: Nobelium isotopes: Plutonium
isotopes: Strutinsky theory: Thorium isotopes: Uranium isotopes.
ABSTRACT: In IPCR cyclotron progress report, 1974.
No. 88
Solov'eva, Z. I.
Radievyj Inst. Leningrad
Probability of the Long-Range Particle Emission in Fission
1973
RI-12; 3 pp.
KEY WORDS: Alpha particles: Californium isotopes: Curium isotopes:
Diagrams: Emission: Fission: Fission yield: Mass: Neptunium isotopes:
Nuclear reactions: Plutonium isotopes: Probability: Range: Thorium
isotopes: Uranium isotopes.
ABSTRACT: An attempt is made to systematize, as a function of the mass
number A presently available, the probability for the emission of long-range
particles Wa(A) during fission. The values of Wa were given graphically
for isotopes of U, Pu, Cf, Np, Cm and Th. (INIS)
No. 89
Marinov, M. S., V. S. Popov, and V. L. Stolin
Institute of Theoretical and Experimental Physics, Moscow
Variational Calculation of the Critical Distance Between Nuclei
1974, January
Jetp Lett. (USSR) (Eng. Trans); 19(1):49-51
56
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KEY WORDS: Boundary conditions: Californium: Curium: Distance:
Fermium: Interaction range: Nuclear reactions: Particle production:
Plutonium: Positrons: Thorium: Uranium: Variational methods.
ABSTRACT: A variational calculation is performed of the critical
distance Rc between colliding nuclei. In this calculation, the principal
term of the quasimolecule (Z,Z,e) drops to the boundary of the lower
continuum, and spontaneous production of positrons begins, (auth)
No. 90
David, F,, K. Samhoun, R. Guillaumont, and L. J. Nugent
Lawrence Berkeley Labs., California University, Berkeley, California
1975, September
LBL-4071; Conf-750913-10; 10 pp.
KEY WORDS: Actinium: Americium: Berkelium: Californium: Curium:
Einsteinium: Enthalpy: Entropy: Fermium: Lawrencium: Mendelevium:
Neptunium: Nobelium: Plutonium: Protactinium: Sublimation: Thermodynamic
properties: Thorium: Uranium.
ABSTRACT: Tabulations were recently published on the enthalpy of
sublimation of the 4f and 5f metals at 298.15K, DELTA HS0(M), and the
standard enthalpy of formation of 298.15K, DELTA HfO(Maq3+), for the
tripositive aqueous metal ions for these two series. Values in this
tabulation for the latter half of the 5f series were not obtained from
experimental measurements, but from theoretical considerations and empirical
correlations drawn from the trends in the 4f series. In the present work new
experimental data were used for the 5f series to modify the empirical
correlations, and tabulate new values for DELTA HfO (Maq3+) and DELTA
HS0(M) for the second half of the 5f series. In addition, values for DELTA
GfO(Maq3+) DELTA GfO equals 3FE°(Maq3+) equals DELTA HfO - T DELTA
SfO for the reaction M + 3Haq+ equals Maq3+ +3/2H2 are given for the
5f series and the oxidation-reduction properties of the 5f elements are
discussed, (auth)
No. 91
David, F., K. Samhoun, R. Guillaumont, and L. J. Nugent
Lawrence Berkeley Lab., California University, Berkeley, California
Some Thermodynamic Properties of 5f Elements
1975, July
LBL-4000; pp. 338-339
57
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KEY WORDS: Actinium: Americium: Berkelium: Californium: Curium:
Einsteinium: Entropy: Fermium: Formation heat: Lawrencium: Mendelevium:
Neptunium: Nobelium: Plutonium: Protactinium: Sublimation heat: Thorium:
Uranium.
ABSTRACT: In nuclear chemistry. Annual report, 1974.
58
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SUBJECT CATEGORY: Analyses (Instrumental)
No. 92
Zalutsky, M. R. and E. S. Macias
Department of Chemistry, Washington University, St. Louis, Missouri
Search for an Anisotropy Between LL X-Rays and Gamma Rays in the Decay of
243Cm
1975, September
Phys. Rev., C.; 12(3): 1076-1079
KEY WORDS: Plutonium-239: Alpha decay: Curium-243.
ABSTRACT: The anisotropy of LL x-rays and Y-rays of 239Pu following
the decay of 243Cm has been investigated. A Ge(Li) crystal with 250 eV
resolution at 5.9 keV was used to detect LL x-rays. A Nal(Tl) crystal was
used to detect six Y-rays between 210 and 285 keV. The measured anisotropy
is A = (3j^6) x 10~3. This is less than 2% of the maximum predicted
anisotropy assuming that the magnetic substate alignment has been completely
retained in the coupling of cascade Y-rays and x-rays, (auth)
No. 93
Zalutsky, M. R., and E. S. Macias
Department of Chemistry, Washington University, St. Louis, Missouri.
Angular Correlation of X-Rays; L-M Cascades of Plutonium
1975, August
Phys. Rev., A.; JL2_(2): 526-530
KEY WORDS: Angular correlation: Plutonium: X-Ray spectra: Curium-243:
Plutonium-239.
ABSTRACT: Angular correlations between L and M x-rays in 239Pu
obtained from a radioactive source of 32-yr 243Cm were measured using
Si(Li) and Ge(Li) detectors. The measured angular-correlation coefficients
A + (8.5 ± 1.5) x 10'2 for the Lpj-M cascade and A22 = (7.7 ± 2.0) x
10~2 for the Lai+2-M cascade are both significantly higher than
theoretical predictions. The intensity of the Pu, \-\-\-3 x-ray per LI
vacancy was found to be I(Li-l_3)/Y(Ll) = (6.6 ± 0.8) x 10'2. The
angular correlation coefficient of the La-(Lj-L3) x-ray cascade was
59
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measured and found to be &22 = (3 ± 7) x 10"2 and is in agreement with
theoretical predictions, (auth)
No. 94
Yates, S. W., A. M. Friedman, and I. Ahmad
Chemistry Division. Argonne National Laboratory, Argonne, Illinois
Octupole State in 246Cm and 248Cm Populated by Inelastic Deuteron
Scattering
1975, September
Phys. Rev., C.; .12(3) :795-800
KEY WORDS: Cross sections: Curium-246: Curium-248: Deuteron
reactions: Energy-level transitions: Inelastic scattering: MeV range
10-100: Parity: Spin: Vibrational states.
ABSTRACT: Vibrational states in 246Cm and 248Cm have been
'Investigated by inelastic deuteron scattering. The K71 = 0-, 1-, and
2-octupole states are identified in 246Cm at 1251, 1080, and 842 keV,
respectively. In 248Cm several excited states above 1 MeV have been
identified; however, definite assignments for these states, except a J11 =
3-state at 1095 keV and a J17 = 2+ state at 1050 keV, could not be made.
Differences between the 24^Cm- and 248Cm-level spectra are interpreted in
terms of their microscopic components. Reduced transition probability B (E3)
is extracted for the observed J11 = 3- levels and is compared with
theoretical values available in the literature, (auth)
No. 95
Porter, F. T., I. Ahmad, M. S. Freedman, J. Milsted, and A. M. Friedman
Chemistry Divsion, Argonne National Laboratory, Argonne, Illinois
Proton States. Anomalous Conversion, and K-Auger Spectra in 241Am from
^4 24E
(Electron Capture) and 24EBk (Alpha) Decays
1974, August
Phys. Rev.,C,; 10/2) : 803-824
KEY WORDS: Americium: Americum-241: Auger effect: Branching ratio:
Energy-level transitions: Internal conversion: Multipolarity:
Nil sson-Mottel son model : Rotational states: Coincidence spectrometry:
Curium-241: Electron capture decay: Electrons: Ft value: Gamma radiation:
Gamma spectra: Half-life: Spectra.
ASTRACT: Gamma and conversion-electron spectra of mass-separated 241Cm
(32.8-day) samples were measured at high resolution with Ge(Li) detectors and
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a magnetic B-ray spectrometer; 28 gamma rays and 75 conversion lines were
identified. The multipolarities of most of the 28 transitions in 241Am
were deduced. Two-parameter Y -y coincidences confirmed a level scheme
incorporating all transitions in six rotational bands. The observed
half-life of 241Cm via the decay of the 471.8 keV Y-ray was 32.8 +. 0.2 day.
The a branching deduced from the measurements of 1-2 and 1.3 electron lines
of the 145.5 keV transition in 237Pu was (1.0 + 0.1)%. The a singles
spectrum of 245Bk (5-day) decay to 241Am showed 12 a groups feeding the 3
lowest bands. On the basis of these measurements six single-particle states
in 241Am have been identified. Tha ground state of 241Am is known to be
5/2'-[523]. The following Nilsson band-head assignments have been made:
(keV, Km(pi) [Nnzx]): 205.9, 5/2 + [642];. 471.8, 3/2-[521]; 632.1, 1/2
+ [400]; 652.1, l/2-[503]; and 670.2 3/2 + [651]. The 266.0 keV El
transition (3/2-[521]—-5/2 + [642]) was found to have the most highly
anomalous conversion coefficient yet observed, with anomaly factors of
100-200, consistent with El penetration conversion parameter sets (gj,
92) = (18.5, 283) or (-19.3, -63); the exiting 205.9-keV El transition (5/2
+ [642]-—5/2-[532]) shows normal El conversion. The 471.8-keV Ml + - 7% E2
transition (3/2 -[521] —5/2-[532]), also shows anomalous (factor of 3)
conversion, with an Ml penetration parameter ~5.5. There is some indication
of anomalously low K conversion for transitions near K threshold. Observed
P! conversion line intensities are about twice the theoretical PI
conversion coefficient predictions. Seven KLL- and two KLM-Auger electron
lines were observed and the K- shell fluorescent yield was deduced as (96.5 +_
0.4)%. (auth)
No. 96
Capgras, A., C. Ronteix, and M. Sueur
Cen De Sacaly, Gif-Sur-Yvette, France
Neutron Spectrum of a 244Cm-Be source by the Recoil Protons Methods and
Determination of the Average Energy EN
1975, May
Int. J. Appl. Radiat. Isot.; 2£(5) .-261-265
KEY WORDS: Beryllium: Curium-244: Energy spectra: Isotope ratio: MeV
range 01-10: Neutron sources: Neutron spectra: Proton recoil detectors.
ABSTRACT: The neutron spectrum of a 244Cm-Be source is determined by
means of an organic liquid scintillator spectrometer. A short description of
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the experimental procedure is given, and the spectrum is compared with the
Am-Be and the Pu-Be spectra. The average energy is En = 3.70 ^0,15 MeV
but is a function of the Cm isotopic composition, (auth)
No. 97
Lorch, E. A.
Radiation Source Department. The Radiochemical Centre, Amersham, Bucks,
England Neutron Spectra of 241Am/B, 241Am/Be, 241Am/F, ^Cm/Be,
238pu/13c anc| 252Cf isotopic Neutron Sources
1973
Intl. J. Appl. Radiat. Isot.: 24:585-591
KEY WORDS: Californium-252: Energy spectra: Neutron sources: Neutron
spectrometers: Stilbene: Americium-241: BCRON: Beryllium: Fluorine:
Curium-242: Carbon-13: Plutonium-238.
ABSTRACT: Neutron spectra form 241Am/B, 241Am/Be, 241Am/F,
242Cm/Be, 238Pu/13C, and 252Cf isotopic neutron sources have been
measured using a spectrometer employing a thin stilbene crystal. The
242Cm/Be spectrum shows marked difference from that of 241Am/Be. The
spectrum from 24^Am/F shows fine structure not previously reported
elsewhere. Differences between the spectra published here and the results of
other workers are attributed to both differences in source and spectrometer
designs, (auth)
No. 98
Rudran, K.
Bhabha Atomic Research Centre, Bombay
Electrodeposition Techniques of Actinides for Bioassay Studies
1972, December
Chemistry Symposium, Vol. II, pp. 185-191
CONF-721239—Pt 2
KEY WORDS: Americium: Ammonium compounds: Bioassay: Curium:
Electro-deposition: Neptunium: Plutonium: Propanols: Protactinium:
Sample preparation: Sulfates: Thorium: Uranium.
ABSTRACT: Trace quantities of actinides present in urine and feces
samples are radiochemically separated and planchetted by electrodeposition
for counting. The method of electrodeposition is discussed. (LK)
62
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No. 99
Schramm, D. N.
University of Texas, Austin
Nucleo-Cosmochronology
1974
Annu. Rev. Aston. Astrophys.; 12:383-406
KEY WORDS: Cosmochemistry: Curium-247: Galactic evolution: Lead-205:
Milky way: Nucleosynthesis: Plutonium-244: R Process: Rhenium-187: S
Process: Samarium-146.
ABSTRACT: Nucleo-cosmochronology is currently capable of obtaining
model-independent results about the age and history of the galaxy. However,
detailed conclusions about galactic evolution cannot at present be given
because of the large uncertainties in the input parameters. Future
measurements, particularly on the 244Pu problem, the development of the
18?Re chronology, and the development of the 247r,m chronology could
enable significant improvement in the state of r-process chronology. The
development of l^Sm as a p-process chronometer and 205pb as an s-process
chronometer would also be an important breakthrough in the field, as would
the development of any other chronometer. With the recent advances in mass
spectrometry it is certain that new developments in this field should be
forthcoming shortly, (auth)
No. 100
Sill, C. W.
Atomic Energy Commission, Idaho Falls, Idaho
Purification of Radioactive Tracers for Use in High Sensitivity Alpha
Spectrometry
1974, September
Anal. Chem.; 46(11):1426-1431
KEY WORDS: Alpha spectroscopy: Americium-241: Americium-243: Aqueous
solutions: Calibration standards: Californium-252: Curium-244:
Evaporation: Neptunium-237: Plutonium-236: Plutonium-239:
Protactinium-231: Protactinium-233: Purification: Stainless steels:
Thorium-234: Tracer techniques: Uranium-232.
ABSTRACT: When several alpha-emitting radionuclides are determined
simultaneously in a single sample by alpha spectrometry, the several tracers
used to determine the chemical yields must each be relatively free of all the
63
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other radionuclides being determined to avoid increasing the uncertainty of
the measurements due to the contaminants added with the tracers. Selected
procedures for purification of tracers of all elements from thorium through
californium are described that have been demonstrated to provide the
necessary decontamination for use in high-sensitivity alpha spectrometry.
Except for protactinium, all final tracer solutions can be evaporated
directly on stainless steel plates to simplify standardization, (auth)
No. 101
Watson, R. L., and T. K. Li
Cyclotron Institute and Department of Chemistry. Texas A M University,
College Station, Texas
Energies and Intensities of Curium L X-Rays Emitted in Coincidence with the
a-Decay of 252Cf
1971, August
Nuc1. Phys. A-178; pp. 201-213
KEY WORDS: Alpha decay: Americium-241: Cal ifornium-252: X-ray
spectra: (a) Internal conversion: (a) Curium-248: (a) Gamma spectra: (a)
Gamma transition: (b) Curium: (b) Fluorescence: (b) X radiation.
ABSTRACT: The energies and intensities of curium L x-rays associated
with the a decay of 252cf were measured with a high-resolution Si(Li)
spectrometer. The measured total intensity of L x-rays was (7.83 _+ 0.40) x
10~2 per a decay. In addition, the Y-ray from the first excited state in
248(;m was observed. The energy of this Y-ray was determined to be 43.399 +
0.025 keV and its intensity is (1.53 ;+ 0.09) x 10~4 per a decay. From the
Y-ray intensity and the a-branching ratio to the first excited state, the
total conversion coefficient for this transition was found to be 1010 +_ 70.
Using the L x-ray and Y-ray intensities, the LH and LHJ subshell
fluoresence yields were derived. The values obtained are W|_n = 0.49 +_
0.04, WLJJ = 0.68 +_ 0.05. As part of the calibration procedure, a
detailed examination of the intensities of Np L x-rays associated with the
a-decay of 241Am was carried out. Results of this analysis are compared
with previously reported intensities which had been renormalized to
approximately correct for large absorption effects, (auth)
No. 102
Zakharov, E. A., B. F. Myasoedov, and I. A. Lebedev
Inst. of Geochemistry and Analytical Chemistry, Moscow
64
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Determination of Americium in Curium by Using Discharge in a Hollow Cathode
1975, July
Zh. Anal. Khim.; 30^(7): 1344-1348
KEY WORDS: Accuracy: Americium: Chemical analysis: Curium: Emission
spectroscopy: Hollow cathodes: Sensitivity.
ABSTRACT: The usage of a hot hollow cathode of a simple geometry permits
the determination of americium (to 1 x 10~7 g) in curium with a coefficient
of variation between 17 and 25%. The variation of transportation of
americium into the hollow cathode plasma is the main factor which influences
the precision, (auth)
No. 103
Zalutsky, M. R.
Washington University, Seattle, Washington
Application of Nuclear Spectroscopic Techniques to Atomic Systems
1974
University Microfilms No. 75-14; 915 pp.
KEY WORDS: Angular correlation: Coster-Kronig transitions: Curium-245:
Energy levels: Europium-153: Neodymium-140: Neodymium-141: Nuclear
structure: Plutonium-239: Probability: Tantalum-181: X-ray spectra.
ABSTRACT: X-ray angular correlations and Coster-Kronig transition
probabilities were measured using cooled, high-resolution Ge(Li) and Si (Li)
spectrometers. Angular correlations between K and L x-rays in ^^Cm,
239pU} 153£U} ancj 181ya were measured. The x-rays of Cm, Pu, Eu, and
Ta were obtained from radioactive sources of 352-yr 2^Cf, 32-yr ^^Cm,
242-day 253Eu, and 140-day 181W, respectively. Several corrections to
the angular correlation coefficients were made including a correction for the
presence of silicon x-ray escape peaks. Angular correlations between L and M
x-rays in 239pu obtained from a radioactive source of ^^Cm were
measured. The anisotropy of LI x-rays and gamma rays of 239pu following
the decay of 243^ nas been investigated. The value of the Coster-Kronig
transition probability for Z equals 73 has been determined by 8 variations of
the K-L x-ray coincidence technique. The effect of a correction for unwanted
L eta-K alpha2 coincidence events in the L alpha-K coincidence spectrum is
discussed. The L2-L3X Coster-Kronig transition probability for Z equals
65
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63, 94 and 96 has been measured in 63Eu was corrected for the presence of
an unresolved L eta x-ray component in the L alpha x-ray group. The reported
values are in agreement with previous measurements but deviate significantly
from theoretical predictions. The nuclear level structure of 140Nd has
been investigated by studying the decay of 5.8-min140m/Pm and 10-sec
140g/Pm with Ge(Li) gamma ray detectors. Decay schemes of 140m/Pm and
140g/pm were constructed. Evidence for low-spin members of the two-phonon
triplet in 140Nd is also presented. In Appendix C, the nuclear level
structure of 141Nd has been investigated by studying the decay of 20.9-min
141Pm produced via the 141Pr(3He, 3n) reaction. From the anti-Compton
spectra and gamma-gamma coincidence measurements a decay scheme has been
constructed which includes 9 previously unreported levels in !41Nd and
incorporates 67 of the 70 gamma rays attributed to the decay of 141Pm. The
results of this work are compared to recent measurements in other N equals 81
isotopes. (Diss. Abstr. Inc., B)
No. 104
Baker, K. R., F. Tolea, R. W. Fink, and J. J. Pinajuan
Georgia Inst. of Technology-, Atlanta: Oak Ridge National Labs, Tennessee
An Experimental Investigation of the Onset of the \-% 13 ffy and
L2~LsM5 Coster-Kronig Transitions from Z GT 90
1974, September
Z. Phys.; 270.: (1)9-15
KEY WORDS: Alpha decay: Coincidence methods: Coster-Kronig
transitions: Curium-244: Plutonium: Plutonium-238: Thorium: Uranium:
Uranium-232: X-radiation: X-ray spectra.
ABSTRACT: L-M coincidence measurements were made on x-rays from the
radioactive decays of 244Cm, 238Pu, and 232U. The observation of M
x-rays in coincidence with 1.3^,5 transition indicates that the onset
of the L2-L-3M5 Coster-Kronig transition takes place at Z = 91 or 92.
The measured ratio of M x-ray counting rates, coincident with the
I-3N4>5 and 1-2 Ify transitions, establishes that both the L2-I-3M4 and the
L2-1-3M5 transitions are energetically possible for Z > = 94, but the
results do not rule out the possibility that these transitions begin as low
as Z = 92. The measurement of L-M x-ray coincidences, together with relative
Coster-Kronig electron intensities from theory or experiment, provides a new
way to measure the total L2-L3 Coster-Kronig transition probability,
66
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F23. at high Z for radioactive sources where the primary vacancies are
created primarily in the 1-2 and 13 subshells. (auth)
No. 105
Dabbs, J. W. T., N. W. Hill, C. E. Bemis, and S. Raman
Oak Ridge National Lab., Tennessee
Fission Cross Section Measurements on Short-Lived Alpha Emitters
1975, March
Conf-740303-55, 2 pp.
KEY WORDS: Alpha particles: Alpha sources: Californium-252: Cross
sections: Curium-245: Fission fragment detection: Fission fragments:
lonization chambers: Methane: Neutron reactions: Performance.
ABSTRACT: The large difference in initial ionization can be used to
limit the size of alpha pulses relative to fission pulses in an ionization
chamber, if the track lengths are both short. In parallel-piate chambers
this condition is not well met. A spherical plate chamber in which the ratio
of maximum/minimum track length is 3 is described. In the present (small
sample) version, the maximum track is 6 mm, with deposit and neutron beam
diameters of 1 cm. At optimum, with pure Cfy gas, an electron collection
time of approximately 22 ns is expected across the 2-mm gap. It is expected
that the worst alpha/fission current plus ratio will not exceed 1/14. Thus
fissile isotopes with alpha half-lives of 30 years or more (e.g., ^^Cm)
may be studied with 1- to 2-nanosecond rise-time current amplifiers; in
addition, very small spontaneous fission branching ratios may be better
determined. Comparisons of this new chamber and initial results on 245cm
(approximately 16-pg sample) are presented. The ORELA-pulsed neutron source
permits measurements below 20 eV which are inaccessible to underground
explosion experiments, (auth)
No. 106
McDonnell, W. R., and T. H. Gould, Jr.
E. I. du Pont de Nemours and Co., Aiken, South Carolina
Surface Blistering of Materials Exposed to 242Cm Alpha Radiations
1975, June
DP-MS-75-7; Conf-750624; 22 pp.
KEY WORDS: Alpha beams: Alpha sources: Containers: Curium-242:
Heating: Helium ions: Physical radiation effects: Platinum: Scaling:
Stainless steel-304: Vanadium: Very high temperature.
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ABSTRACT: A study was conducted to establish the extent of surface
deterioration of container materials for 242Cm and 252Cf caused by
implantation of high concentrations of helium resulting from the alpha decay
of the radionucl ides. It was found that materials implanted with helium from
alpha-emitting nuclide sources are much less susceptible to surface
blistering at low temperature than materials implanted with accelerator
helium ions, probably because of a more uniform distribution of helium within
the implanted surface layer. On post-irradiation heating to high
temperature, however, a porous surface layer is formed, (auth)
No. 107
Liukkonen, E., V. Metag, and G. Sleetten
Niels Bohr Institutete, Copenhagen, Denmark
Recoil Escape Efficiencies and Ranges of Actinide Recoils from Actinide
Targets
1975, March
Nucl. Instrum. Methods; 125(1):113-117
KEY WORDS: Alpha reactions: Americium ions: Americium oxides:
Americium-241: Americium-242: Charged-particle transport: Compound-nucleus
reactions: Curium ions: Curium-240: Deuteron reactions: Efficiency:
Neutrons: Plutonium oxides: Plutonium-238: Proton reactions: Protons:
Range: Recoils: Thickness.
ABSTRACT: Escape efficiencies of recoiling Cm and Am nuclei with
energies of 50 to 400 keV from Pu and Am targets have been measured. Recoil
ranges for curium ions in plutonium and americium dioxide are deduced. The
experimental results are compared with predictions of the Linhard, Scharff
and Schiott theory. The calculated ranges are in reasonable agreement with
the experimental values, (auth)
No. 108
Samhoun, K., and F. David
California University, Lawrence Berkeley Lab., Berkeley, California
Radiopolarography of Am, Cm, Bk, Cf, Es, and Fm
1975, September
LBL-4070; Conf-750913-11; 7 pp.
KEY WORDS: Americium: Aqueous solutions: Berkelium: Californium:
Curium: Einsteinium: Electrochemistry: Francium: Polarography.
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ABSTRACT: The standard electrode potentials determined in this work are
affected by the accuracy of determining delta £2 and delta £3, since
these energies of amalgamation were estimated by correlation with those of
some 4f elements. The accuracy on the measured half-wave potential itself is
5 mV for all elements, Bk and Cm excepted. Finally, we note that these
standard potentials are in good agreement with those calculated by
correlating the variaton in P(M) function for 4f and 5f series, (auth)
No. 109
Ahmad, I., F. T. Porter, M. S. Freedman, R. K. Sjoblom, J. Lerner, R. F.
Barnes, J. Milsted, and P. R. Fields
Chemistry Division, Argonne National Laboratory, Argonne, Illinois
Levels in 237Pu Populated by 237Am (Electron Capture) and 241Cm (alpha)
Decays
1975, August
Phys. Rev., C.; 12(2}:541-552
KEY WORDS: Americium-237: Electron capture decay: Gamma radiation:
Gamma spectra: Half-life: Plutonium-237: Alpha reactions:
Compound-nucleus reactions: Curium-241: Neutrons: Plutonium-239.
ABSTRACT: The electron capture decay scheme of 237Am (73 min) has been
investigated by measuring the ^-ray and conversion-electron spectra of
mass-separated 237Am samples. The f-ray spectra were measured with a
Ge(Li) spectrometer and the conversion-electron spectra were measured with a
cooled Si(Li) detector and a magnetic g-particle spectrometer. Thirty-five
Y-rays were identified and the multipolarities of most of the transitions
were deduced. The half-life of 237Am was determined by following the decay
of the 280.2 keV photopeak and was found to be 73.0 +_ 1.0 min. The
a-particle energy and a-branching were measured to be 6.042 +_ 0.005 MeV and
[(2.5 +_ 0.3) x 10~2]%, respectively. On the basis of the present
investigation the following single-particle states have been identified in
237Pu: 7/2-[743], 0; l/2+[631], 145.5; 5/2+[622], 280.2; 3/2+[631], 370.4;
5/2+[633], 407.8; 7/2+[624], 473.5; 5/2-[752], 655.3; and 7/2+[613], 908.8
keV. The ground state of 237Am has been deduced to be the 5/2-[523]
Nilsson orbital. The log-ft values for electron capture transitions to the
observed states were derived. The a-particle spectrum of a mass-separated
sample was measured with the Argonne double-focusing magnetic
69
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spectrometer. Eleven a groups identified in this spectrum populate the
members of the ground state, l/2+[631], and 3/2+[631] bands. The a-decay
hindrance factors are consistent with the Nilsson-state assignment deduced
from 237^m electron capture decay, (auth)
No. 110
Aleksandrova, Z. A., V. I. Bol'shov, V. F. Kuznetsov, G. N. Smirenkin, and M.
Z. Tarasko
Prompt Neutron Spectra from Spontaneous Fission of 252Cf, 244Cm, and
1974, April
At. Energ. (USSR) ; 36.(4) :282-285
KEY WORDS: Cal ifornium-252: Curium-244: Energy spectra:
Plutonium-240: Prompt neutrons: Spontaneous fission.
ABSTRACT: Prompt neutron spectra for spontaneous fission of
^Cm, and 2^Pu in the neutron energy interval 1 to 14 MeV were
determined by using a single-crystal scintillation spectrometer based on
stilbene with time discrimination of gamma-quanta emission. The results
exhibit a Maxwell ian-type distribution. For these three isotopes, the
parameters of this distribution are determined and compared with data given
in the literature, (auth)
No. Ill
Argonne National Laboratory, Argonne, Illinois
Separations and Environmental Chemistry
1974, June
ANL-8153, pp. 7-17
KEY WORDS: Americium: Berkelium: Californium: Chromatography:
Curium: Diffusion: Plutonium: Radioactive wastes: Radionuclide migration:
Rocks.
ABSTRACT: Progress in research on high-speed radiochemical separations
by liquid-liquid chromato.graphy is reported. Results of the separation of
Am(III) and Cm(III) and the separation of Bk(III) and Cf(III) are given.
Application of liquid-liquid extraction to disposal of reactor waste is
considered. In the study on the behavior of plutonium and americium in rock
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strata, the major research effort was aimed at evaluating techniques of
measuring the parameters relevant to the migration of the two elements. (LK)
No. 112
Tyufyakov, N. D., A. S. Shtan, V. S. Yaskevich, A. G. Kozlov, V. B.
Pavlovich, L. A. Trykov, and S. G. Tsypin
Russia
Investigation of the Spectral Characteristics of Neutron Sources Based on
238Pu> 244Cm and 252Cf
1975, May
AEC-TR-7314, pp. 86-93
KEY WORDS: Beryllium: Californium-252: Curium-244: Lithium fluorides:
Neutron sources: Neutron spectra: Plutonium-238.
ABSTRACT: Neutron spectra data are given for the neutron sources:
238Pu + L1F. 238Pu + Be; 244Cm + Be; 244Cm. and 252cf. (TFD)
No. 113
Pyper, D. M., and M. R. Hartoog.
University of Wisconsin-Parkside
Heavy Elements in the Peculiar A Star HD 25354
1975, June
Astrophys. J.; .198(3):555-559
KEY WORDS: Americium: Cerium ions: Chemical composition: Curium:
Dysprosium ions: Elements: Emission spectra: Europium ions: Hoi mi urn:
Mercury: Neodymium ions: Platinum: Samarium ions: Stars: Thorium.
ABSTRACT: The spectrum of the Sr-Cr-Eu Ap star HD 25354 shows strong
lines of Eu^j, Dyu, Ndjj, and Smji. Lines of Hgu and PTji are
probably present and Ujj is possibly present but very weak. Our results
disagree with an earlier line identification of HD 25354 by Jaschek and
Brandi in that we find no Th, Am, or Cm lines, and in that Ho lines are not
unusually strong on our spectrograms. The apparent overabundances of Hg and
Pt in HD 25354 as well as in several other Ap stars of the Cr-Eu type may
imply that these stars represent a transition between two groups: Ap stars
having abundance anomalies in Si, Fe-peak elements, and the rare earth
elements; and the Hg-Mn Ap stars, (auth)
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No. 114
Thompson, R. C., J. R. Huizenga, T. W. Elze, and J. P. Unik
Univ., Frankfurt Am Main
Rochester University, New York
Collective State Populated by Inelastic Deuteron Scattering on Even-Even
Actinide Nuclei
1975
Coo-3496-50, pp. 11-16
KEY WORDS: Coulomb excitation: Curium-248: Deuteron reactions:
Deuterons: Energy levels: Inelastic scattering: MeV range 10-100:
Plutonium-240: Plutonium-244: Thorium-230.
ABSTRACT: In studies of nuclea'r fission, low energy nuclear reactions
and transuranic nuclei. Progress report 1 June 1974 - 1 June 1975.
(Rochester Univ., New York).
No. 115
Baker, K. R., F- Tolea, R. W. Fink, and J. J. Pinajian
Georgia Inst. of Tech., Atlanta: Oak Ridge National Laboratory, Tennessee
Mean M-Subshell Fluorescence Yield at Z = 88, 90, 92, and 94
1974, September
Z. Phys.; 270(1):l-7
KEY WORDS: Coincidence methods: Fluorescence: X-ray spectra: Alpha
decay: Curium-244: Plutonium-238: Thorium-228: Uranium-232: X-radiation.
ABSTRACT: M x-ray - L x-ray coincidence measurement with
high-resolution, cooled Si(Li) x-ray detectors were made on transitions
following the alpha decays of 228Th, 232U, 238Pu, and 244Cm, in order
to determine the mean M-subshell fluorescence yields. Furthermore, the
nonradiative M-shell transition probability and the radiative \-\-L$
transition probability were measured for Z = 88, 90, 92, and 94 and compared
with calculations of McGuire and of Scofield. (GE)
No. 116
Kerrigan, W. J., and C. J. Banick
E. I. du Pont de Nemours and Company, Aiken, South Carolina
Calorimetric Measurement of Alpha Half-life of 242Cm
1975, March
I. Inorg. Nucl. Chem.; 37(3):641-643
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KEY WORDS: Alpha decay: Calorimetry: Curium oxides: Curium-242:
Half-Life: Power: Radiation sources.
ABSTRACT: The alpha half-life of 242Cm was found to be 163.2 + 0.4
days by calorimetric determination of the change in power of two curium oxide
sources over a period of 287 days, (auth)
No. 117
Thompson, R. C., J. R. Huizenga, and T. W. Elze
Nuclear Structure Research Laboratory, University of Rochester, New York
Collective States in 230Th, 240Pu, 2^4Pu and 248Cm Excited by
Inelastic Deuteron Scattering
1975, October
Phys. Rev., C.; ,12(4) :1227-1235
KEY WORDS: Collective model: Cross sections: Curium-248: Deuteron
reactions: Energy spectra: Energy-level transitions: Inelastic scattering:
MeV range 10-100: Parity: Plutonium-240: Plutonium-244: Probability:
Spin: Thorium-230: Vibrational States.
ABSTRACT: Energy spectra of inelastically scattered 16-MeV deuterons
were measured at angles of 90° and 125° using enriched targets of 23OTh,
240pu, 244Pu, and 24^Cm. In each nucleus the ground state band is
observed up to and including the J17 = 8+ level. The g vibration j-7r = 0+
level is identified in 230~Th, and this and the remaining three nuclei
evidence for the Y vibration is discussed. At least octupole bands are
observed in each nucleus and K.J* assignments are made in a number of
cases. B (ED) and B(E3) values are extracted for selected levels, (auth)
No. 118
Carnall, W. T., and K. Rajnak
Chemistry Division, Argonne National Laboratory, Argonne, Illinois
Electronic Energy Level and Intensity Correlations in the Spectra of the
Trivalent Actinide Aquo Ions. II. CM3"1"
1975, October
J. Chem. Phys.; 63(8):3510-3514
KEY WORDS: Absorption spectra: Aqueous solutions: Cations: Chlorates:
Curium compounds: Energy levels: Oscillator strengths.
ABSTRACT: The free-ion energy level scheme of Cm3"1" (aquo) to 40,000
cm"! was determined. Energy level assignments were made based on the
correlation between observed band intensities and those calculated using the
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Judd-Ofelt theory. Use of an expanded set of effective operators provided
the basis for computation of free-ion energies in good agreement with the
experimental assignments, (auth)
No. 119
Burnes, J. H., J. N. Stevenson, and J. R. Peterson
Oak Ridge National Labs., Tennessee _
Crystallographic Studies of Some Transuranic Trihalides: 23yPUCLJ,
2«CMBR$, 249BKBR3, and 249CFBR3
1975, March
J. Inorg. Nucl. Chem.; 37_(3):743-749
KEY WORDS: Berkelium bromides: Berkelium-249: Bond lengths:
Californium bromides: Californiurn-249: Coordination valences: Crystal
lattices: Curium bromides: Curium-244: Molecular structure: Monocrystals:
Plutonium chlorides: Plutonium-239: Structural chemical analysis: X-ray
diffraction.
ABSTRACT: Single-crystal x-ray diffraction methods were used to refine
the structure of PuCl3, CmBr3, and CfBrs. In PuCl3 (UCl3-type) the
Pu ion has nine Cl-ion neighbors, three at 2.919(1)^ and six at
2.886(1)A. A radius of 0.995 A* was derived for the six-coordinated
Pu^+ ion. In CmBr3 (PuBr3-type) the eight-coordinated Cm ion has two
Br ions at 2.865(6)51, four at 2.983(4)A, and two at 3.137(4)A.
Californium tribromide was shown to crystallize in both the A1C13- and
FeCl3-type structures. In the former type, the Cf ion is six-coordinated
and the three independent Cf-Br bond lengths are 2.795(9)^, 2.827(11)A
and 2.828(8)A. Berkelium tribromide was prepared and shown by powder
x-ray diffraction to exhibit the A1C13-, PuBr3~, and possibly
FeCl3-type structures. The new findings on CfBr3 and BkBr3 were used
to produce a more complete description of the structure relationships among
the lanthanide and actinide tribromides. (auth)
No. 120
Bibler, N. E.
E. I. duPont de Nemours and Company, Aiken, South Carolina
Fission Fragment Radiolysis of 0.4M Sulfuric Acid Solutions with Dissolved
252(;f
1974, July
DP-MS-74-4; Conf-740715-5, 19 pp.
74
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KEY UORDS: Absorption spectroscopy: Alpha particles: Californium-252:
Cerium compounds: Chemical radiation effects: Curium-244: Fission
fragments: G Value: Hydrogen: Hydrogen peroxide: Hydroxyl radicals: Iron
compounds: LET: Peroxy Radicals: Radiolysis: Sulfuric Acid.
ABSTRACT: Radiolysis of 0.4M sulfuric acid solutons at very high LET
values ( 400 eV A) was studied with fission fragments from dissolved 252Cf.
This isotope irradiates the solution with both fission fragments and alpha
particles. Visible and UV absorption spectroscopy were used to determine
G(Fe3+) in KT3M Fe2+ G(Ce3+) in KT4M Ce4+/lQ-3M Ce3+, and G(Ce3+) in
10-4M Ce4+/103+M Ce3+ containing lO"3 or 10~2M Tl+. Values for
G(h2) were determined manometrically. Experiments with alpha particles
(LET* 9 eV/A) from dissolved 244Cm verified the technique and established
100 eV yields (G values) for pure a-radiolysis. Experiments with mixtures of
244Cm and 2^2Cf established that the effects of fission fragments and
alpha particles are independent. The following results were obtained for
G(Fe3+), G(Ce3+), G(Ce3+) in 0.001 M Tl+, and G(h2), respectively:
for4 244Cm-5.1, 2.9, 3.3, 1.3; for 252Cf-4.4, 2.7, 2.9, 1.8; for fission
fragments-3.3, 2.4, 2.4, 2.1. Interpretation of the fission fragment-yields
leads to the following estimates: G(H2) = 2.1, G(H202) = 1.0, G(H02)
= 0.5, G(OH) - 0, and G(H) = 0. (auth)
No. 121
Chuveleva, E. A., 0. V. Kharitnov, V. M. Gelis, P. P. Nazarov, and K. V.
Chmutov Inst. of Physical Chemistry, Moscow
Chromatographic Separation of Curium, Americium, and the Lanthanides with the
aid of Organophosphorus Complexones
1974, November
Russ. J. Phys. Chem.; 48(11):1673-1675
KEY WORDS: Americium: Chromatography: Complexes: Curium: Phosphonic
acid esters: Rare earths: Trace amounts.
ABSTRACT: Microamounts of curium, americium, and the lanthanides were
separated chromatographically with the aid of Organophosphorus complexones at
room temperature and 70° C. The separation factors and the height equivalent
to the theoretical plate (HETP) were determined, (auth)
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No. 122
Chuveleva, E. A., P. P- Nazarov, and K. V. Chmutov
Inst. of Physical Chemistry, Moscow
Chromatographic Separation of Curium, Americium, and the Lanthanides with the
Aid of Diethylenetriaminepentaacetic and Nitrilotriacetic acids
1974, December
Russ. J. Phys. Chem. (Engl. Trans!.); 48(12):1799-1800
KEY WORDS: Americium: Chromatography: Curium: DTPA: Europium:
Medium temperature: Neodymium: NTA: Promethium: Samarium: Yttrium.
ABSTRACT: The separation factors for curium, americium, and certain
lanthanides in the presence of diethylenetriaminepentaacetic and
nitrilotriacetic acids were determined by elution chromatography at 25° C and
70° C. (auth)
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SUBJECT CATEGORY: Analyses (Chemical)
No. 123
Lisin, S. K., L. N. Morozov, V. I. Novgorodtseva, V. A. Pchelin, L. V.
Chistyakov, V. A. Shigin, and V. M. Shubko
Institute of Atomic Energy, Moscow
Mass Distribution of 252Cf Fission Fragments
1975, June
Yadern, Fiz.; 21_(6) :1178-1184
KEY WORDS: Alpha reactions: Antimony-127: Antimony-129: Cadmium-115;
CaMfornium-252: Cerium-141: Cerium-143: Cerium-144: Curium-248:
Distribution: Excitation: Fission: Fission fragments: Fission yield:
Mass: Molybdenum-99: Palladium-112: Silver-Ill: Silver-113:
Spontaneous fission: Strontium-89: Strontium-91: Tin-121: Tin-125.
ABSTRACT: The radiochemical method is used to measure the mass
distributions of "2Cf fission fragments at various excitation energies.
The nucleus 2^2Cf was produced via bombarding the 2/^Cm nuclei with a
particles; at the a-particle energies of 24, 29, and 34 MeV the 252Cf
fission keeps being asymmetrical. The widths of the mass peaks at the
half-height are 22, 25, and 28 mass units; the peak-to-dip ratios are,
respectively, 3.5, 2.0 and 1.7. Variation of the 252Cf mass distribution
when the energy increases is not consistent with predictions of the
statistical model, (auth)
No. 124
Gedeonov, L. I., I. G. Gritchenko, T. P. Makarov, A. M. Maksimova, and A. V.
Stepanov
U.S. AEC Technical Information Center, Oak Ridge, Tennessee (translation)
Radiochemical Method of Determination of Uranium, Neptunium, Plutonium,
Transplutonium, and Rare Earth Elements in Samples of Aerosols, Radioactive
Fallout, and Soil.
1973
AEC-TR-7566, 14 pp.
KEY WORDS: Alpha spectroscopy: Americium: Americium-241: Aqueous
solutions: Benzene: Beta spectroscopy: Cerium: Chemical analysis:
Curium: Curium-242: EDTA: Electrophoresis: Ethyl ether: Europium:
Fallout: Gamma spectroscopy: Ion exchange: Ion exchange chromatography:
Isotope ratio: Lanthanium: Neodymium: Neptunium: Neptunium-237:
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Neptunium-239: Organic ion exchangers: Plutonium-239: Plutonium-240i
Praseodymium: Promethium: Promethium-147: Quantitative chemical analysis:
Radioactive aerosols: Radiochemical analysis: Soils: Solvent extraction:
TTA: Uranium: Yttrium: Yttrium-90.
ABSTRACT: This method can be used for the determination of isotopes of
neptunium, plutonium, americium, curium, uranium, and rare earth elements in
samples of aerosols, radioactive fallout, and soil. The method is based on
the extraction of uranium VI by ether, selective separation of neptunium from
plutonium III, americium, curium, rare earth elements and other fission
fractions by extraction with a 5% solution of tenoyltrifluoracetone in
benzene, chromatographic separation" of plutonium (VI) from trivalent
actinides and rare earth elements in a solution of 8M nitric acid with
subsequent electromigration separation. The chemical yield of the elements
listed above, with a reliability of 0.67, is as follows: for uranium (90 +_
3%), neptunium (75 +; 4%), plutonium (75 +; 4%), americium, curium and rare
earth elements - (60 +_ 5%). The time required for the radiochemical
analysis is 7 hours, including the time required for dissolving the sample,
whose weight must not exceed 1 gram. The radio-metric determination of the
isotopic composition of the separated elements is carried out with the aid
of gamma and alpha spectrometers. The sensitivity of the method in the
determination of active isotopes 239"240Pu, 241Am, 242Cm and others is
2 • 10'12 curies/g; beta-active isotopes 90Y, 147Pm-5 • 10~10
curies/g. (auth)
No. 125
Ramaniah, M. V.
Bhabha Atomic Research Centre, Bombay
Radiochemical Studies of the Actinides
1972, December
Conf-721239-Pl, pp. 133-182
KEY WORDS: Americium: Curium: Fission: Isotope production:
Neptunium: Physical properties: Plutonium: Radiochemistry.
ABSTRACT: A review is presented of the work being done at the Bhabha
Atomic Research Centre on the radiochemistry of the actinides. As the
chemistry of U and Th is widely studied, the present work concentrates on the
fission and radiochemistry of Pu, Np, Am and Cm. The production and physical
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properties of the actinides is first briefly summarized, and the facilities
available at Trombay are indicated. The fission studies and chemical studies
are described in some detail. (JSR)
No. 126
Zalutsky, M. R., and E. S. Macias
Washington University, St. Louis, Missouri
Experimental Determination of the 1-2-1-3X Coster-Kronig Transition
Probability in Europium, Plutonium, and Curium
1975, January
Phys. Rev., A.; n.(l) :71-74
KEY WORDja: Coincidence methods: Coster-Kronig transitions: Curium:
Electronic structure: Europium: Plutonium: Probability: X-radiation.
ABSTRACT: The 1-2-1-3 X Coster-Kronig transition probability for Z =
63, 94, and 96 was measured by the L-x-ray-K-x-ray coincidence technique.
The value measured in ^Eu was corrected for the presence of an unresolved
Ln x-ray component in the La x-ray group. The values reported are for
63Eu, F23 = 0.172 +0.015, for 94Pu, f23 = 0.233 +_ 0.015, and for
96Cm, f23 = 0.226 +0.017. (auth)
Mo. 127
McGowan, F. K., C. E. Bemis, Jr., W. T. Milner, J. L. C. Ford, Jr., R. L.
Robinson, and P. H. Stelson
Oak Ridge National Laboratory, Tennessee
Coulomb Excitation of Vibrational-Like States in the Even-A Actinide Nuclei
1974, September
Phys. Rev., C.; 10_(3): 1146-1155
KEY WORDS: Alpha reactions: Coulomb excitation: Inelastic scattering:
MeV range 10-100: Multipolarity: Parity: Probability: Spin: Vibrational
states: Uranium isotopes: Thorium-230: Curium isotopes.
ABSTRACT: Coulomb excitation of vibrational-1ike states in the even-A
actinide nuclei (230
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relative to the elastic scattering by the observation of elastically and
inelastically scattered 4He ions using a split-pole magnetic spectrometer
equipped with a position-sensitive proportional detector. The values of
B(Ex, Og-- J = X) range from 0.5 to 4 single-particle units for X = 2 and
from 10 to 30 single-particle units for X = 3. For those cases, where the K,
Jir assignments are known, the agreement between the experimental results and
the microscopic calculations by Neegard and Vogell of the B(E3, 0 —- 3) for
the 3- members of the one-phonon octupole quadruplet is good when the
Coriolis coupling between the states with K and K +. 1 is taken into account.
The magnitudes of the reduced EO nuclear matrix elements, p (EO, 2 — 2g),
extracted from the EO transition probabilities, T(EO, 2 — 2g) for decay
of the e-vibrational-like 2+ state, are 0.37 +; 0.06 and 0.43 +_ 0.06 for
232fh and 238^ respectively. Several 2+ states observed in this Coulomb
excitation reaction survey are presumed to be 2+ members of rotational bands
based on 0+ excited states which are strongly populated in the (p,t)
reaction, (auth)
No. 128
Chmutova, M. K., N. P. Nesterova, 0. E. Koiro, and B. F- Myasoedov
Inst. of Geochemistry and Analytical Chemistry, Moscow
Solvent Extraction of Trivalent Transplutonium Elements and Eu with
Aklylenediphosphine Dioxides from Nitric Acid Solution
1975, June
Zh. Anal. Khim.; 30(6):1110-1115
KEY WORDS: Americium: Berkelium: Californium: Curium: Europium:
Nitric acid: Phosphines: Quantity ratio: Solvent extraction.
ABSTRACT: The solvent extraction of trivalent Am, Cm, Bk, Cf, and Eu
with five different tetraarylalkylenediphosphine dioxides was examined from
0.5 to 15.7 M HN03 solutions. The previously reported regularities of
changing the extraction power of the reagents of this group with their
structure describe only the extraction from relatively weakly acid media but
not that from strongly acid media. The separation factors for all the
reagents studied depend on HN03 concentration. They are very small in the
extraction from 0.5 to 4.0 M HN03 and reach the maximum values at HN03
concentration of 15.7 M. The reagent selectivity and the order of the
80
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extraction of the elements depend mainly on the structure of the bridge
between the P + 0 groups, (auth)
No. 129
Chmutova, M. K., B. F. Myasoedov, B. Ya. Spivakov, N. E. Koechetkova, and Yu.
A. Zolotov
Inst. of Geochemistry and Analytical Chemistry, Moscow
Solvent Extraction of Transplutonium Elements by the Mixture of
Tri-n-Octylamine with Neutral Extractants from Nitrate Solutions
1971, December
J. Inorg. Nucl. Chem; 35^:1317-1326
KEY WORDS: Americium: Americium complexes: Americium-241: Anions:
Aqueous solutons: Californium: Californium complexes: Californium-250:
Callfornium-252: Complexes: Curium: Curium complexes: Curium-244:
Europium: Europium complexes: Europium-152: Ligands: Mixtures: Nitrates:
Solvent extraction: Synergism: TBP: IDA: TOPO: TPO.
ABSTRACT: Using 241Am, 244Cm, 250,252cf and 152Eu> the soivent
extraction of the trivalent transplutonium elements and europium from nitrate
solutions into mixtures of tri-n-octylamine (TOA) with tri-n-butyl phosphate
(TBP) and other neutral extractants in different solvents has been studied.
A synergistic effect has been found for mixtures of TOA with TBP,
tri-n-octylphosphine oxide and triphenylphosphine oxide, (auth)
No. 130
Foos, J., and R. Guillamont
Paris university, Orsay, France
Solvent Extractions of Cis- and Trans-uranium Elements from Fuse Alkali
Nitrates
1974, December
I. Inorg. Nucl. Chem.; 36(12):3833-3837
KEY WORDS: Actinium: Americium: Californium: Curium: Eutectics:
High temperature: Lithium nitrates: Molten salts: Neptunium: Partition:
Plutonium: Polyphenyls: Potassium nitrates: Solvent extraction: TBP:
Thorium: TPO: Uranium.
ABSTRACT: Solvent extraction of Ac, Th and 5f elements up to Cf at 150°
C from a molten LiN03-KN03/v2 eutectic by TBP or TPPO in a polyphenyl
mixture has been studied. Plots of the log distribution coefficients of
these elements vs the log-free TBP or TPPO concentration in the organic phase
81
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are reported, except for Pa which is not extracted. The behavior of Th in
extraction from such a system is different from that of other elements.
(auth)
No. 131
Mayasoedov, B. F., M. K. Chmutova, H. E. Kochetkova, and G. A. Pribylova
Inst. of Geochemistry and Analytical Chemistry, Moscow
Extraction of Trivalent Transplutonium Elements and Europium by a Mixture of
Di-2-Ethylhexylorthophosphoric Acid and Phosphorus Pentoxide from Strongly
Acid Media
1974
Conf-740917-P2, pp. 1103-1108
KEY WORDS: Americium: Berkelium: Californium: Curium: Cyclohexane:
Europium: HDEHP: Hydrochloric acid: Nitric acid: Perchloric acid:
Phosphorus oxides: Solvent extraction: Sulfuric acid.
ABSTRACT: The extraction of trivalent transplutonium elements and
europium from solutions of inorganic acids by a mixture of di-2-
ethylhexylorthophosphoric acid (D2EHPA) and ?2®5 i"1 cyclohexane was
investigated. It was shown that the proposed mixture of reagents
quantitatively extracts Am and Eu from solutions of acids of sufficiently
high concentration. Large amounts of aluminum and ammonium nitrates, at
D2EHPA and Vfls concentrations equal to 0.3 M and 0.11 M respectively,
do not interfere with extraction. The extractant exhibits low selectivity
with respect to trivalent transplutonium elements, (auth)
No. 132
Umezawa, H., S. I. Ichikawa, and H. Natsume
Japan Atomic Energy Research Inst., Tokyo
Cation-Exchange Separation of the Transplutonium and Rare Earth Elements
1974, July
JAERI-M-5785, 11 pp.
KEY WORDS: Americium: Cations: Cerium: Curium: Europium:
Hydrochloric acid: Ion exchange: Ion exchange chromatography: Particle
size: Quantitative chemical analysis: Resins: Yttrium.
ABSTRACT: Various gel- and porous-type resins were tested for use in the
cation-exchange chromatography with an eluent of 11.7 M hydrochloric acid.
When gel-type resins were used, very fine resins, such as colloidal
82
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aggregate, were needed to perform good separation. The lower cross-linkage
resins provide the larger number of theoretical plates of the column, but the
distribution coefficients and separation factors become smaller. While those
coefficients obtained with the porous-type resin were similar to those
obtained with the gel type of the same cross-linkage, the number of
theoretical plates for the porous type increased by a factor of about 3 and
tailing in the elution curve decreased remarkably. Three groups of Am-Cm, Y,
and Eu-Ce can be well separated by using a 4-mm diameter by 20-cm height
column of a porous-type resin, DIAION CPK08, 35 y, with 11.7 M hydrochloric
acid, (auth)
No. 133
Zaitsev, A. A., I. I. Nazarova, I. V. Petukhova, V. T. Filimonov, and G. N.
Yakovelv
Nauchno-issledovatel'skij Inst. Atomnykh Reaktorov, Dimitrovgrad (USSR)
Extraction by Phosphororganic Acids. Part 1. Effect of the Phosphonic Acid
Ester Composition and Structure on Trivalent Cation Extraction
1973
NIIAR-P-210, 15 pp.
KEY WORDS: Americium: Berkelium: Californium: Curium: Distribution
functions: Europium: Hydrochloric Acid: Nitric acid: Organic Phosphorus
compounds: Perchloric acid: Promethium: Separation processes: Solvent,
extraction: Solvent properties: Yttrium.
ABSTRACT: A study was carried out on the extraction of americium,
curium, berkelium, californium, promethium, europium, and yttrium with
diethyl benzene solution of n-amyl, isoamyl, n-octyl, 2-ethylhexyl, and
n-decyl esters of phenylphosphoric acid [C^s (RO)P(O) (OH)] over a wide
interval of acidity (0.1 to 8 M) of perchloric, nitric and hydrochloric
acids. By these studies it was possible to establish regularities associated
with the structure and composition of the esters. Lengthening the ester
radical from C$ to CIQ leads to an increase in extractability of the
phosphonates. On the other hand, branching of the ester radical near the
phosphorous atom decreases the extractability of the phosphonates, with the
extraction of curium decreasing more rapidly than the extraction of
californium with a resulting improvement in the separation of these elements.
In addition, the nature of the mineral acid has a significant effect on the
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distribution of elements and on their separation. The following order for
change in values of the distribution and separation coefficients of
californium and curium was established: HC104 > HC1 > HN03. (tr-auth)
No. 134
Zaitsev, A. A., I. I. Nazarova, I. V. Petukhova, V. T. Filimonov, and G. N.
Yakovlev
Russia
Extraction by Organophosphorus Acids. I. Effect of Composition and
Structure of Phosphonic Esters on the Extraction of Trivalent Cations of
Transplutonium and Rare Earth Elements
1974
Sov, Radiochem. (Engl. Transl.) 16.(2): 177-180
KEY WORDS: Americium: Amend urn complexes: Berkelium: Berkelium
complexes: Californium: Californium complexes: Curium: Curium complexes:
Europium: Europium complexes: Hydrochloric acid: Nitric acid: Perchloric
acid: Phosphonic acid esters: Promethium: Promethium complexes: Solvent
extraction: Yttrium: Yttrium complexes.
ABSTRACT: It was shown that isoesters of phenylphosphonic acids are more
promising for the separation of the pair californium-curium than the normal
esters. It was shown that lengthening the ester radical from C5 to CIQ
leads to an increase in the extraction power of the phosphonates. Branching
of the ester radical reduces the extraction power of the phosphonates with
the extraction of curium falling more rapidly than that of californium,
leading to an improvement in their separation. It was shown that the nature
of the mineral acid affects to a considerable degree the distribution of the
elements and also their separation. The following order was established for
the distribution coefficients and the separation factors of californium and
curium: HC104 > HC1 > HN03- (auth)
No. 135
Szeglowski, Z.
Institute of Nuclear Physics, Krakow (Poland)
Physicochemical Investigations on the Extraction Mechanism of Some Elements
and Inorganic Acids by Quaternary Ammonium Salts
1974
Inst. Nucl. Phys.; IFJ-863, 116 pp. In Polish.
KEY WORDS: Americium: Bismuth: Cerium: Chemical properties: Chemical
reaction kinetics: Chloroform: Curium: Europium: Hydrochloric acid:
84
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Lanthanum: Lead: Neodymium: Neptunium: Nitric acid: Plutonium:
Polonium: Praseodymium: Promethium: Pyridinium compounds: Quaternary
compounds: Samarium: Solvent extraction: Solvent properties: Thallium:
Uranium.
ABSTRACT: The extraction of rare earth and transplutonium elements, Tl,
Pb, Bi, and Po, and also of HN03 and HC1, with chloroform solutions of
cetylpyridinium slats was investigated. Measurements of conductivity and
light absorption by cetylpyridinium salts solutions showed that the salts
aggregate in chloroform solutions, forming micelles above a concentration of
about 10~2 M. Surface tension and surface potential measurements proved
that cetylpyridinium nitrate is not" transferred to HNC>3 solutions in the
extraction system, while cetylpyridinium chloride is transferred to HC1
solutions, (auth)
No. 136
Ueno, K., K. Watanabe, C. Sagawa, and T. Ishimori
Japan Atomic Energy Research Institute, Tokai
Separation of Transplutonium Elements from Neutron-Irradiated Americium-241
1973, January
J. Nucl. Sci. Technol. (Tokyo); U_(l):8-14
KEY WORDS: Americium: Americium oxides: Californium: Curium: Fission
Products: Ion exchange: Isotope production: Mass spectroscopy:
Multielement analysis: Neutron beams: Plutonium.
ABSTRACT: The isotopes of transplutonium elements were produced by
irradiation of 10.5 mg of 241/^02 in the Japan Materials Testing Reactor
during the period May 1970 through June 1971. Transplutonium elements were
separated from plutonium, fission products, and cladding materials by a
combination of precipitation and ion exchange methods. Americium, curium,
and californium were mutually isolated by ordinary procedure.
Plutonium-238-242, americium-241-243, and curium-242-245 were detected in the
plutonium, americium, and curium fractions, respectively. The ratios of the
amounts present of these isotopes were determined by mass spectrometry. It
was not possible to identify 249Bk in the berkelium fraction owing to the
interference from other e-particle emitting nuclides. In the californium
fraction, both spontaneous fission and a-activities due to 250,252r,f Were
observed, (auth)
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No. 137
Abdel-Latif Bilal, B., K. Metscher, B. Muhlig, C. Reichmuth, and B. Schwarz
Hahn-Meitner-Institut Fuer Kernforschimg Berlin, Germany
Application of Counter-flow Ion Migration for Separation of Actinides
1973
Chem. Ing. Tech.; 45_(12) :841-846
KEY WORDS: Americium: Aqueous solutions: Curium: Isotope production:
Neptunium: Plutonium: Radioactive waste processing: Reprocessi'ng:
Separation processes: Spent fuels: Targets: Uranium.
ABSTRACT: The method of counterflow ion migration in aqueous solutions
is proposed for separation of the actinides from the hot waste from the
reconditioning of spent nuclear fuels as well as for the working or
irradiated transuranium targets such as 237Np, 241>243Am, 239Pu and
242Pu used in obtaining the nuclides that serve as energy or neutron
sources. A laboratory-scale separation procedure that seems to be universal
and suitable for this task, which is based on the difference in ion
mobilities, was developed and was first tested in cold operation on the
laboratory scale, (auth)
No. 138
Shafiev, A. I., Yu. V. Efremov, and G. N. Yakovlev
Nauchno-Issledovatel'skij Inst. Atomnykh Reaktorov, Dimitrovgrad (USSR)
Influence of Zirconium Phosphate Treatment on Efficiency of Americium(V),
Separation from Curium(III), and Evolution of Berkelium(IV) and Cerium(IV)
1974
NIIAR-p-224; 11 pp.
KEY WORDS: Adsorbents: Americium: Berkelium: Cations: Cerium:
Chemical preparation: Curium: Data: Purification: Separation processes:
Transuranium elements: Zirconium phosphates.
ABSTRACT: Data are presented that show the effect of the method of
processing of zirconium phosphate on the efficiency of separation of Am(V)
and Cm(III), and of Bk(IV) from Ce(IV). Impurities with reducing properties
in the zirconium phosphate may be removed by a several-cycle treatment, e.g.,
dissolving in IN HN03 and 5% (NH4)2S203 at 80-90° C and then in IN
HN03 followed by drying in air and heating at 100-270° C for 5 to 7 hrs.
For separating Am(V) from Cm(III), the sorbent must be converted to the
cation form, (tr-auth)
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No. 139
Mason, G. W., A. F- Bollmeier, and D. F. Peppard
Chemistry Division, Argonne National Laboratory, Argonne, Illinois
Partition of Oxidized Americium from Actinides(III) and Lanthanides(III)
1969, August
J. Inorg. Nucl. Chem.; 3^:1011-1022
KEY WORDS: Actinides: Alkyl radicals: Americium: Curium: Esters:
Methyl radicals: Nitric acid: Organic Phosphorus compounds: Rare earths:
Separation processes: Solvent extraction: Valence: Water: Potassium
compounds: Silver nitrates: Persulfuric acids: Heptyl radicals.
ABSTRACT: In the liquid-liquid extraction system 0-6 F bis (2,6-dimethyl
4-heptyl) phosphoric acid (C9H190)2PO(OH), HD(DIBM)P, in n-heptane vs.
an aqueous 0-025 F HNOs + 0.025 F AgN03 + 0.085 F K2S208 phase the
K for oxidized Am, presumably Am(IV), is greater than 40 while that for
Cm(III) is less than 1 x 10"^. Correspondingly, the K values for each
M(III) actinide and lanthanide tested is less than 1 x 10~3. Consequently,
this system may be used for the purification of americium with respect to
M(III) actinides and lanthanides or alternatively for the purification of
M(III) actinides and lanthanides with respect to americium. Details of the
mutual separation of 241^ ancj 244Qm through the application of this
liquid-liquid extraction system are given. Proposed extension of the study
to extraction chromatography employing HD(DIBM)P as the stationary phase is
discussed, (auth)
No. 140
Lebedev, I. A., V. I. Chepovoii, and B. F. Myasoedov
Inst. of Geochemistry and Analytical Chemistry, Moscow
Berkelium and Cerium Oxidation by Sodium Perxenate in Nitrate Solutions
1975, August
Radiochem. Radioanal. Lett.; 22J4):239-242
KEY WORDS: Berkelium: Berkelium-249: Cerium: Curium-244:
Europium-155: Nitric acid: Oxidation: Oxygen compounds: Sodium compounds:
Xenon compounds.
ABSTRACT: With the addition of sodium perxenate to solution of Ce(III)
and diluted HN03, curium can be oxidized to Ce(IV) forming a precipitate.
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This precipitate coprecipitates indicator amounts of 249Bk, but not 155Eu
and 244Cm which indicate berkelium oxidation to Bk(IV). (auth)
No. 141
Lyle, S. J.
Surrey University, Guildford, England
Solvent Extraction in Inorganic Analytical Chemistry
1973
Sel. Annu. Rev. Anal. Sci.; 3^:1-57
KEY WORDS: Actinium: Americium: Beryllium: Boron: Cadmium:
Californium: Cerium: Cesium: Chemical analysis: Chemical reaction
kinetics: Curium: Europium: Hafnium: Indium: Iodine: Laboratory
equipment: Lanthanum: Lutetium: Molybdenum: Neptunium: Niobium:
Plutonium: Polonium: Protactinium: Reviews: Rhenium: Ruthenium:
Scandium: Solvent extraction: Strontium: Tantalum: Tellurium:
Thermodynamic properties: Thorium: Thulium: Tungsten: Uranium: Vanadium:
Yttrium: Zirconium.
ABSTRACT: The subject is reviewed under the following headings: general
reviews and monographs; laboratory apparatus and techniques; kinetic aspects
of extraction; some thermodynamic properties, solubility and salt effects;
equilibrium and mechanistic aspects of extraction; appl ications(separation
and concentration; determination of the metal in the non-aqueous phase). The
elements covered include the following: Be, B, Cd, Cs, Ce, Eu, Hf, In, I,
La, Lu, Mo, Nb, Re, Ru, Sc, Sr, Ta, Te, Tm, V, W, Y, Zr, Am, Ac, Cf, Cm, Np,
Pa, Po, Pu, Th, and U. (UK)
No. 142
Foos, J.
Paris-11 University, Orsay, France
Solvent Extraction of Rare Earth and Actinide Elements from Molten Salts
1974
IPNO-T-74-10, 110 pp.
KEY WORDS: Actinium: Americium: Berkelium: Californium: Cations:
Cerium: Chemical reaction kinetics: Curium: Distribution functions:
Dysprosium: Erbium: Europium: Gadolinium: Holmium: Infrared spectra:
Lanthanum: Lithium nitrates: Lutetium: Molten salts: Neodymium:
Neptunium: Partition: Plutonium: Polyphenyls: Potassium nitrates:
Praseodymium: Promethium: Protactinium: Samarium: Solvent extraction:
Synergism: TBP: Terbium: Thorium: Thulium: TPO: TTA: Ultraviolet
spectra: Uranium: Ytterbium.
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ABSTRACT: The mechanisms of solvent extraction from molten eutectic
LiN03-KN03 by TBP, TPPO or TTA diluted in a polyphenyl mixture were
studied. The distribution coefficients of lanthanides, actinium, thorium and
5f series elements up to californium were measured at 150° C by a, p, or
radiometry, according to the nuclides which were used. Trivalent elements
easily oxidizable to 4 oxidation state have a behavior dependent on their
concentration and affinities with oxide anions. Some spectrophotometric
studies (UV or IR) were investigated, in order to study, first the
interactions of matter with neodymium nitrate in the fused salt, then the
solvating nitrate in polyphenyl mixture. In the case of TTA extraction, the
H+ ions released by the chelate formation are fixed by the oxide ions and
lead peculiarly to the NC>2 and 02 formation. So the distribution of the
solvated cations depends on the gaseous phase composition. This last becomes
an equilibrium agent and gives a great deal of applications to this system.
(Fr)
No. 143
Haidvogel, N., G. Reitsamer, and F. Grass
Holland
Sorption of Plutonium and Curium on Ion Exchange Resins in Mixed Aqueous
Organic Solutions
1973
Lib Trans-544, 27 pp.; Atomkernenergie, 22_(2) :117-127
KEY WORDS: Alcohols: Americium: Americium nitrates: Americium
sulfates: Americium-241: Aqueous solutions: Autoradiography: Curium:
Curium nitrates: Curium sulfates: Curium-242: Ion exchange: Mixed
solvents: Organic ion exchangers: Plutonium: Plutonium nitrates:
Plutonium-239: Resins: Thin-layer Chromatography.
ABSTRACT: The sorption of the sulfate and nitrate complexes of the
actinides Pu(III), Pu(IV), Pu(VI), Am(III) and Cm(III) on the ion-exchange
resins Dowex 1x8 and Dowex 50WX8 was investigated. The strong sorbability of
these actinide ions in solvents with high contents of alcohol is explained by
2-the existence of anionic complexes like Pu(III) (SO,;)2', Pu(IV) ($04)3,
Pu(V)02(S04)2~, Am (S04)2- on Am (N03)4- and Cm(N03)4-. The taking of
autoradiographs from the thin-layer chromatograms by the aid of a special
device and the evaluation of the autoradiographs by a particular
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photodensitometer are described. The measurement of the radioactivity of
the a-emitting nuclides 239Pu, 241Am and 242Cm is done by liquid-
scintillation spectrometry. (auth)
No. 144
Guseva, L. I,, and G. S. Tikhomirova
USSR
Isolation of Transplutonium Elements on Anionities by Means of Aqueous
Alcohol Solutions of Nitric Acid and Ammonium Thiocyanate
1974
Sov. Radiochem. (Engl. Transl.); 16:153-156
KEY WORDS: Americium: Ammonium compounds: Californium: Cerium:
Curium: Europium: Hydrochloric acid: Ion exchange: Methanol: Organic
ion exchangers: Thiocyanates.
ABSTRACT: An investigation was made of the effect of the alcohol
content, the NfyCNS concentration, HC1, and the nature of the alcohol in
the solution on the distribution coefficients of curium and europium and also
the half-width of the elution curve of Eu from anionites containing 4 and 8%
divinylbenzene. It was shown that the group separation of TPE and REE is
best carried out with methanol solutions on NH/jCNS acidified with HC1 and
resins with a lower content of divinylbenzene, since in this case the
elements are eluted on a narrower front and the separation is sharper. A
method is proposed for isolating transplutonium elements from a large number
of elements of the Periodic Table with the simultaneous separation of the
light TPE on anionites by means of an aqueous alcohol solution of nitric acid
and ammonium thiocyanate. (auth)
No. 145
Ikeda, N., K. Kimura, and G. Ichikawa
Japan Atomic Energy Research Inst. Tokyo
Mutual Separation of Aqueous Heavy Ions By Paper Electrophoresis
1973
JAERI-m-5567; pp. 333-337
KEY WORDS: Americium: Anions: Curium: Electric potential:
Electrophoresis: Monocarboxylic acids: Neptunium: pH value: Plutonium:
Protactinium: Separation processes: Thorium: Uranium.
ABSTRACT: Rapid mutual separation of three heavy ion groups (Th-Pa-U;
U-Np-Pu; Am-Cm) was achieved by means of paper electrophoresis. The paper
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used was 2.5-cm x 25-cm Cellogel strip, the buffer solution 0.5 to 0.8 M
a-hydroxy iso-butylic acid solution with pH 2.0 to 3.0, and the applied
voltage 2000 V. It took only 25 to 30 min for complete separation of the
elements of each group, (auth)
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SUBJECT CATEGORY: Chemical (Animal)
No. 146
Delle Site, A., G. Santori, and C. Testa
Cnen, Casaccia, Italy
New Simple Methods for the Determination of Some Actinide Elements in
Bioassays
1973, March
Conf-730345-P2, pp. 761-775
KEY WORDS: Americium: Bioassay: Chemical analysis: Curium: HDEHP:
Neptunium: Nitric acid: Plutonium: Radiation monitoring: Radiometric
analysis: Radionuclide kinetics: Sensitivity: Solvent extraction:
Thorium: TOPO: Uranium: Urine.
ABSTRACT: The internal contamination due to alpha emitters must be
evaluated by the determination of these elements in the excreta. Especially
in cases of suspected acute contamination, the determination of some
actinides (plutonium, americium, curium, neptunium) in the urine has to be
carried out within a few hours to decide whether a therapeutical treatment
with DTPA is necessary. Furthermore the presence of the chelating agent
generally causes serious interference when the most common method reported in
the literature is used. Therefore some new radiotoxicological techniques
were prepared by the Radiotoxicological Laboratory of the Casaccia Nuclear
Centre of CNEN (Rome) for the rapid determination of thorium, uranium,
Plutonium, americium, curium, and neptunium in urine. All these methods are
based on a batch extraction of the radionuclides from the wet mineralized
urine by means of an organic extractant supported on a microporous polymer.
Tri-n-octylphosphine (TOPO) and di-2- ethylhexylorthophosphoric acid (HDEHP)
were used as the selective extractants, and a powder of microporous
polyethylene (Microthene-710) was employed as the inert support. The urine
is mineralized by boiling with nitric acid and stirred for 20 to 60 minutes
with the slurry Microthene-TOPO (for uranium, thorium, plutonium and
neptunium) or Microthene-HDEHP (for americium and curium); the slurry is then
transferred quantitatively into a chromatographic column and, after washing,
the element is selectively eluted with a suitable solution. When
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the urgency is great, the alpha counting can be carried out directly by a
ZnS(Ag) detector; however a greater sensitivity limit can be achieved by
electroplating the radionuclide and counting with a solid state detector; in
this case alpha spectrometry can also be carried out. Thorium can be
determined better by final colorimetry with Arsenazo III. The final yields
for enriched uranium, plutonium, neptunium, americium and curium range from
70 to 85% with a general sensitivity limit of about 0.1 pCi for a 24-hour
sample; thorium gives a yield of 90% and a sensitivity limit of 0.2 yg/1.
The blank values are sufficiently low and the decontamination factors are
generally very high. The time required for one analysis ranges from 3 to 8
hours. As the extraction of the radionuclides is carried out in a nitric
acid medium, DTPA does not interfere with the analysis. This technique
yielded excellent results also on the occasion of an IAEA intercomparison
related to radiotoxicological analyses of human urine, (auth)
No. 147
Eakins, J. D., and P. J. Gomm
Health Physics and Medical Division, Berkshire, England
The Determination of Gross Alpha Activity in Urine by Adsorption on Glass
Fibre Filter Paper
1967, September
Health Physics, 14:461-472
KEY WORDS: Valence: pH filters: Alpha particles: Urine: Adsorption:
Thorium: Protactinium: Neptunium: Plutonium: Americium: Curium: Ion
exchange: Methods.
ABSTRACT: A description is given of work carried out to determine the
optimum conditions for maximum surface adsorption of a number of alpha
emitting radioelements on glass fiber filter paper. The effect of valence,
pH and presence of pyrophosphate is discussed and a new technique for the
determination of gross alpha activity in urine is given based on surface
adsorption. Overall recoveries of thorium, protactinium, neptunium,
plutonium, americium and curium are about 80% using this procedure. The
advantages of surface adsorption over conventional ion exchange are discussed
and the development of other procedures based on this principle is suggested.
(auth)
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SUBJECT CATEGORY: Biological (Effects)
No. 148
Craig, D. P., J. F. Park, and J. L. Ryan
Battelle Pacific Northwest Labs., Richland, Washington
Effect of Physico-chemical Properties on Metabolism of Transuranium Oxide
Aerosols Inhaled by Beagle Dogs
1975, October
BNWL-SA-5430; Conf-751073-1, 28 pp.
KEY WORDS: Americium oxides: Americium-241: Beagles: Biological
Half-life: Chemical Properties: Curium oxides: Curium-244: Dogs:
Inhalation: Lungs: Particle size: Plutonium oxides: Plutonium-238:
Plutonium-239: Radioactive aerosols: Radionuclide kinetics: Retention
functions: Tissue distribution.
ABSTRACT: The oxides of four transuranium isotopes (238Pu, 239Pu,
241Am, and 244Cm), prepared by identical methods of calcining the oxalate
at 750° C for 2 hours, had different physico-chemical properties. For all
four oxides the density ranges from 9.8 to 11.4 g/cm~3 and initial
ultrafilterability (suspended fraction of activity less than 24 A) varied
from 0.002 percent for 239Pu02 to 2.24 percent for 238Pu02. Dogs
were exposed by nose-only techniques to aerosols generated by nebulizing
water suspensions of the oxides. The dogs were sacrificed at intervals from
one week to about a year postexposure. The rate of translocation of material
from the lung to other tissues increased from 239Pu to 238Pu to 24lAm
to 244Cm, possibly reflecting the decrease in mean particle size from an
MMD of 0.7 ym for 239Pu02 to 0.6 pm for 238Pu02 to 0.4 ym for 241Am02 to
0.1 um for 244CmOx. Accumulation of the isotopes in the liver and
skeleton as a percentage of final body burden was 1 percent 239Pu and 7 to
23 percent for 238Pu at about a year postexposure, while at 270 days
postexposure, values were 40 percent for 241Am and 40 to 30 percent for
244Cm. (auth)
No. 149
Dougherty, J. H.
Utah University, Salt Lake City, Utah
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Early Hematologic Effects of Curium and Einsteinium in Beagles
1974, March
COO-119-249, pp. 268-280
KEY WORDS: Alpha sources: Beagles: Biological radiaton effects:
Blood formation: Bone tissues: Curium-243: Curium-244: Dose-response
relationships: Einsteinium-253: Hematopoietic system: Injection:
Internal irradiation: Radionuclide kinetics: Single intake: Time
dependence: Tissue distribution: Uptake.
ABSTRACT: The hematologic changes following a single injection of curium
(244Cm + 243Cm) at tne 5_dose level, or einsteinium (253Es) at the 3-
and 5-dose levels, into a small number of adult beagles have been summarized
for the first 9 to 12 months following injection. These actinide elements
are surface-seeking alpha emitters with the einsteinium having a very short
half-life (20.5 days). The early hematologic effects follow the typical
patterns of early granular leukocyte and erythrocyte depression as seen after
injection of high dose levels of other transuranic elements. However, the
rates and magnitude of recovery of the various cells are much more rapid in
dogs injected with the short-lived 253[[S> (auth)
No. 150
Lafuma, J.
CEA Centre D'etudes Nucleaires de Fontenay-Aux-Roses, France
Inhaled Radioelements
1974, March
Radioprotection; £(l):15-25
KEY WORDS: Americium-241: Biological radiation effects: Carcinomas:
Curium-244: Dose-response relationships: Inhalation: Lungs: Plutonium-
Radioinduction: Radon-222: Rats.
ABSTRACT: The results described fall within the framework of long-
term research aiming at studying the pathological effects of inhaled
radioelements, namely plutonium-239 oxide, americium-241 nitrate and curium-
244 nitrate. A DL = 50 value was determined for each radioelement and for
each physical-chemical form. This DL = 50 rises from the curium-244 nitrate
to the plutonium-239 oxide. The differences observed are linked to the
number of cells affected, which depends on the degree of heterogeneity of
radioelement distribution. Many cancers were obtained during the
experiments. These cancers had histological types identical to certain human
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cancers. Irrespective of the dose, the first animals to die showed
metaplases, those living on had non-malignant tumors, and it is in those
living the longest that cancers were found. This systematic succession of
celluar damage foreshadows the possibility of interpreting the various
different mechanisms entering into cancer induction. (FR)
No. 151
Sanders, C. L., and G. E. Dagle
Battelle Pacific Northwest Labs., Richland, Washington
Studies of Pulmonary Carcinogenesis in Rodents Following Inhalation of
Transuranic Compounds
1974, June
BNWL-SA-4925; Conf-740648-3; 18 pp.
KEY WORDS: Alpha sources: Biological radiation effects:
Carcinogenesis: Chronic irradiation: Curium oxides: Curium-244: Dose
rates: Dose-response relationships: Inhalation: Internal irradiation:
Intratracheal administration: Low dose irradiation: Lung clearance: Lungs:
Microspheres: Neoplasms: Pathological changes: Plutonium oxides:
Plutoriium-238: Plutonium-239: Radiation dose distributions: Radiation
doses: Radioinduction: Respiratory system: Retention: Uptake.
ABSTRACT: The influence of absorbed radiaton dose and its distribution
on pulmonary carcinogenesis in rats was examined following inhalation of
238pu from crushed 238puQ2 microspheres, 238pu02, or ^Cm02 and following
intratracheal instillation or inhalation of 239puo2« A more uneven
dose-distribution (e.g., 238puQ2 or 239pu02) favors squamous carcinoma
induction at high doses, while adenocarcinoma induction is greater at lower
doses or at all doses following a more even dose-distribution in the lung
(e.g., 238pUj 244Qm02). Squamous metaplasia and adenomatosis appeared
to precede the development of squamous carcinoma and adenocarcinoma,
respectively. Pulmonary hemangiosarcomas were found only after high doses
of inhaled 239Pu02- These results demonstrate the importance of dose and
dose-distribution on the development of pulmonary tumors from inhaled a
emitters, (auth)
No. 152
Bair, W. J.
Battelle Pacific Northwest Labs., Richland, Washington
1975, April
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Biological Effects of Transuranium Elements in Experimental Animals
BNWL-SA-5339; CONF-750436-1; 96 pp.
KEY WORDS: Alpha particles: Americium-241: Biological radiation
effects: Body burden: Carcinogenesis: Chronic irradiation: Curium-242:
Dose-response relationships: Inhalation: Injection: Internal irradiation:
Laboratory animals: Plutonium-238: Plutonium-239: Radiation doses:
Radioinduction: Radionuclide administration: Radionuclide kinetics: Skin
absorption: Tissue distribution.
ABSTRACT: Results are reported from life span studies of the biological
effects of the transuranium elements (238Pu, 239Pu, 241Am, and 242Cm)
on laboratory animals following inhalation, skin absorption, or injection in
various chemical forms. The dose levels at which major biological effects
have been observed in experimental animals are discussed relative to the
maximum permissible lung burden of 0.016 uCi for occupational exposures.
Lung cancer has been observed at dose levels equivalent to about 100 times
the maximum permissible lung burden. Current experiments directed towards
determining whether health effects will occur at lower levels and the
mechanism by which alpha emitters induce cancer are reviewed. (CH)
No. 153
Bair, W. J.
U.S. AEC, Washington, D.C.
Battelle-Pacific Northwest Labs., Richland, Washington
Biological Effects of Transuranium Elements in Experimental Animals
1974, December
WASH-1359, pp. 171-229
KEY WORDS: Alpha sources: Americium-241: Biological radiation effects:
Curium-244: Dogs: Dose-response relationships: Einsteinium-253:
Ingestion: Inhalation: Internal irradiaton: Laboratory animals:
Pathological changes: Plutonium-238: Plutonium-239: Polonium-210: Skin
absorption: Tissue distribution: Transuranium elements.
ABSTRACT: Radiation hazards to man from the transuranium elements
involve occupational exposures in the work environment and hazards to the
general population from exposure to very low levels of the transuranium
elements. The major health effects of the transuranium elements are due to
their emission of a radiation and the nature of the effects depends upon
which tissues are irradiated following deposition in the body. Data are
reviewed from studies in laboratory animals of the tissue distribution and
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late pathological effects of transuranium elements following inhalation,
ingestion, or deposition on skin. Extensive data are summarized on 238pu
and 239Pu in dogs, and limited data are presented on the tissue
distribution and pathological effects of 244Cm, 241Am, and 253Es in
dogs and other animals. (CH)
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SUBJECT CATEGORY: Biological (Animal-Metabolism-Retention)
No. 154
Madhavanath, U., M. S. S. Murthy, R. R. Vishwakarma, P. Suberahmanyam, and G.
C. Das
Bhabha Atomic Research Centre, Bombay
Alpha Contamination of the Skin: Dose and LET Distribution at Depths
Corresponding to the Epidermal Thickness of Skin
1974, November
Health Phys.; £7(5):469-474
KEY WORDS: Alpha particles: Contamination: Curium-242: Depth dose
distributions: Dose rates: Epidermis: LET: Maximum acceptable
contamination: MeV range 01-10: Polonium-210: Quality factor: Radiation
doses: Skin: Thickness.
ABSTRACT: Recently it has been reported that the thickness of the
epidermal layer of skin can be as low as 2-4 mg/cm2 in certain parts of the
body (Harvey, 1971; Whitton, 1971; Whitton, 1973). In these areas, alpha
contamination could result in the irradiation of basal layer cells. In order
to evaluate the associated hazard, the energy distribution and dose of alpha
particles from 210p0 ancj 242r,m have t>een measured at various depths. By
computing the LET distribution, the Quality Factor (OF) for alpha irradiation
of basal cells has been calculated to be 20. If an average epidermal
thickness of 4 mg/cm2 is accepted for radiation protection purposes
(Whitton, 1973), contamination by alpha particles for energy 5.7 MeV and
above can result in the irradiation of basal layer cells. For the current
permissible skin contamination value of 10~5 mCi/cm2, the dose rate at
this depth from 242Cm (6.11 MeV) is about 45 mrem/hr. Thus the dose to the
skin becomes the limiting factor for arriving at the permissible skin
contamination. Hence it is desirable to lower the contamination level for
energetic alpha particles, (auth)
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No. 155
Craig, D. K., 0. R. Decker, G. J. Powers, and J. F. Park
Battelle Pacific Northwest Labs., Rich!and, Washington
Disposition of Highly Toxic Radioactive Aerosols Inhaled by Beagle Dogs
1975, July
BNWL-SA-5170; Conf-750707-2; 20 pp.
KEY WORDS: Americium-241: Beagles: Curium oxides: Curium-244:
Excretion: Inhalation: Liver: Lungs: Muscles: Particle size: Radiation
dose distributions: Radioactive aerosols: Radionuclide administration:
Radionuclide kinetics: Retention: Skeleton: Time dependence: Tissue
distribution.
ABSTRACT: Beagle dogs were exposed to 241Am or 244Cm oxides in an
apparatus which permitted separation of expired from inspired air and
measurement of these volumes, the aerosol concentrations, and their size
distributions. Following exposure, excreta were collected and analyzed for
30 days and for a week prior to sacrifice. Activity in the lungs was
estimated from periodic thorax counts, while complete tissue analyses were
conducted on groups of 3 dogs sacrificed 10, 30, 90 and 270 days
postexposure. Indications from the early thorax counts, excreta, and tissue
analyses showed the 244CmOx aerosols having AMAD equals 0.5 \im and GSD
equals 2.1, initial alveolar deposition varied from 40 percent for the low
level (10 nCi) to 20 percent for the high level (400 nCi); after early
ciliary clearance, as much 244Cm was excreted in the urine as in the feces;
at 10 days postexposure, 25 to 35 percent was still in the lung with 45 to 65
percent in other soft tissues and 10 to 30 percent in the skeleton. For
24lAm02, tne slze distribution was a function of aerosol concentration,
with AMAD equals 0.7 um and GSD equals 2.4 at the low level (1 nCi),
increasing to 1.35 urn and 1.7 at intermediate levels (125 nCi), and 1.45pm
and 1.7 at the high level (1150 nCi); corresponding mean alveolar depositions
were 15, 30, and 35 percent. The 241Am or 244Cm tissue distribution
analyses at various times postexposure showed that both isotopes are readily
translocated from the lungs to liver, skeleton, and muscle, 244Cm twice as
rapidly as 241Am. (auth)
100
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No. 156
Kotrappa, P.
Lovelace Foundation for Medical Education and Research, Albuquerque, New
Mexico
Production of Relatively Monodisperse Aerosols for Inhalation Experiments by
Aerosol Centrifugation
1971, October
Health Physics; 21=531-535
KEY WORDS: Particle size: Plutonium-239: Plutonium-238: Americium-
241: Curium-244: Lungs: Dogs: Beagle: Deposition: Aerosols:
Inhalation.
ABSTRACT: Stober's aerosol spectrometer, based on a spinning spiral
duct, was used as an aerosol centrifuge to separate narrow size groups of
insoluble aerosols starting from polydisperse distributions. The samples
collected were resuspended in water and aerosolized with a Lovelace nebulizer
to produce relatively monodisperse aerosols. Working with near-spherical
fused clay particles, aerosols were obtained with geometric standard
deviations of less than 1.1 and with number concentrations which would be
practical for use in inhalation experiments. A formula for dilution of
monodisperse suspensions for aerosolization was used to calculate the maximum
number concentration that could be aerosolized from a suspension for a
particular nebulizer to obtain 95% singlets. This method appears to be
particularly adaptable for aerosols of oxides of transuranic elements.
Estimated respiratory depositions of the oxides of 239pu> 238pu> 241/\m
for Beagle dogs breathing the mono-disperse aerosols for 1 hour are given for
aerodynamic sizes ranging from 0.5 mm to 3.0 mm. (auth)
No. 157
Lloyd, R. D., D. R. Atherton, C. W. Mays, S. S. McFarland, and J. J. Williams
Utah University, Salt Lake City, Utah
Early Excretion, Retention, and Distribution of Injected Curium Citrate in
Beagles
1974, July
Health Phys.; 27(l):61-67
KEY WORDS: Beagles: Citrates: Curium compounds: Curium-243:
Curium-244: Feces: Intravenous injection: keV range 100-1000: Liver:
Radionuclide kinetics: Renal clearance: Retention: Skeleton: Spatial
distribution: Thyroid: Time dependence: Urine: Whole-body counting.
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ABSTRACT: The behavior of curium has been studied in five young adult
beagles from 0 to 57 days after the intravenous injection of 244r,m +
243Cm in citrate buffer. Total excretion during the first 3 weeks after
injection was mainly urinary. Of the entire Cm eliminated in this 3-week
collection period, nearly 3/5 appeared in the first day's urine. About five
times more curium was excreted in the urine than in the feces on the first
day. Following this, however, partitioning of curium between urine and feces
in the daily excretion was more nearly equal. A combination of total-body
and partial-body counting of the living dogs utilizing the 209, 228, and 278
keV gamma-rays of 243(;m indicated t-hat at a week after injection about 35%
of the injected Cm was deposited in the liver and about 53% was in non-liver
tissue (mainly skeleton). Three of the dogs were sacrificed, one each at 6,
13, and 20 days after injection. Although the liver and skeleton accounted
for the bulk of the retained curium, some other tissues exhibited significant
Cm concentrations, particularly the thyroid, (auth)
No. 158
Lloyd, R. D., and C. W. Mays
Utah University, Radiobiology Division, Salt Lake City, Utah
Determining Liver Retention of Transuranium Elements in Living Beagles
1975, July
Radiat. Environ. Biophys.; _12(2):139-145
KEY WORDS: Americium-241: Beagles: Californium-247: Californium-252:
Curium-243: Liver: Plutonium-237: Radionuclide kinetics: Retention:
Tracer techniques: Whole-body counting.
ABSTRACT: A method has been developed whereby the liver content of
photon-emitting transuranium elements can be determined in living beagles by
a combination of total-body and partial-body counting. Calibration of the
system was accomplished through the photon counting of intact dogs and also
of the parts of the same animals following autopsy. A determination of the
calibration factors for 252cfj 247cfj 243Cm> 237pUj and 241Am nas
been made. The special case of 252Cf was treated in which a significant
fraction of the high energy fission gamma-ray spectrum penetrates the Pb
shield employed in partial-body counting, and methods were developed which
allow for this effect in the calculation of liver content. Some uniformity
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of response in the system was evident for all of the emitters which were
considered. It is proposed that similar techniques could be applied in the
determination of selected organ radioactivity in other species including man.
(auth)
No. 159
Mays, C. W., R. D. Lloyd, and D. R. Atherton
Utah University, Radiobiology Division, Salt Lake City, Utah
1974, March
COO-119-249. pp. 308-310
KEY WORDS: Americium-241: Beagles: Californium-249: Californium-252:
Curium-243: Curium-244: Gonads: Intravenous injection: Plutonium-239:
Radionuclide kinetics: Retention: Tissue distribution: Uptake.
ABSTRACT: Young adult beagles were injected intravenously with
transuranium elements in citrate solution. Data are presented on the gonadal
retention of 239Pu, 241Anlj 243Cm> 244Cm> 249Cf} and 252Cf from j to 2127 days
after injection. (CH)
No. 160
Moskalev, Yu. I., G. A. Zaiikin, and A. I. Semenov
Moscow
Kinetics of 244r,m Accumulation in Organs and Tissues of Rats in Chronic
Introduction of the Isotope into the Body
1974, June
Gig. Sant.; No. 6, pp. 41-43
KEY WORDS: Chronic intake: Curium-244: Kidneys: Liver: Radionuclide
kinetics: Rats: Skeleton.
ABSTRACT: The kinetics of 244Cm accumulation in case of chronic
subcutaneous introduction of the isotope was studied in experiments performed
on rats. The data show that an intensive accumulation of 244cm takes place
for 32 to 64 days. The amount of isotope accumulated was determined in the
liver, kidneys, and other organs; however, in the bone it never attained a
balanced level during 256 days of the experiment. The possible reasons for
the low 244Cm deposit in the skeleton in case of chronic introduction of
the isotope are discussed, (auth)
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No. 161
Nenot, J. C., M. Morin, W. Skupinski, and J. Lafuma
Commissariat a 1'Energie Atomic, France
Experimental Removal of 144Ce, 241Am, Z42Cm and "8Pu from the Rat
Skeleton
1972, February
Health Physics, j!3:635-640
KEY WORDS: Americium-241: Cerium-144: Curium-242: DTPA:
Plutonium-238: Inhalation: Intramuscular injection: Rats.
ABSTRACT: The therapeutic effectiveness of DTPA on bone deposits of
lanthanide or transuranic elements .can be appreciable when the greater part
of the activity is to be found in bone. This was obtained after 3 weeks time
following the administraton by inhalation of ^44Ce and 24lAm and by
intramuscular injection of 242Cm and 238Pu. DTPA therapy starting after
this delay decreased bone burdens by a factor from 1/2 to 1/3 in 3 months.
There probably exists two different compartments which would clear, under the
influence of DTPA, with a half-life of 2 months for the former and very
slowly for the latter. The effectiveness of DTPA on the second compartment
could not be estimated, (auth)
No. 162
Sullivan, M. F., and A. L. Crosby
Battelle Pacific Northwest Labs., Richland, Washington
Absorption of Uranium-233, Neptunium-237, Plutonium-238, Americium-241,
Curium-244, and Einsteinium-253 from the Gastrointestinal Tract of Newborn
and Adult Rats
1975, March
1); pp. 105-108
KEY WORDS: Age dependence: Americium-241: Curium-244:
Einsteinium-253: Gastrointestinal tract: Intestinal absorption: Liver:
Neptunium-237: Nitrates: Oxides: Plutonium-238: Radiation hazards:
Radionuclide kinetics: Rats: Retention: Skeleton: Uranium-233.
ABSTRACT: Absorption of the nitrates of 233U, 237Np, 238Pu, 241Am,
244Cm, and 253Es by the adult rat was estimated at 0.03%, 1.0%, 0.006%,
0.012%, 0.04%, and 0.014%, respectively; absorption of the oxides of 241Am
and 244Cm was estimated at 0.01% and 0.003%, respectively. These estimates
are based on retention in skeleton and liver. Absorption of the nitrates of
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237Np, 238pUj 241^ 244r,m> and 253Es by the newborn rat was estimated at
6.6%, 2.9%, 5.0%, 2.0%, and 5.1% respectively; absorption of the oxides of
241Am and 244Cm was estimated at 1.1% and 1.7%, respectively. The amount
retained by the lower small intestine of newborn rats was frequently several
times more than the amount absorbed, which could be a significant factor in
evaluating the hazard potential of these radionuclides. (auth)
No. 163
Seidel, A., and V. Volf
Kernforschungszentrum Karlsruhe, Irrstitu fur Strahlenbiologie, Republic of
Germany
Removal Of Internally Deposited Transuranium Elements by Zn-DTPA
1972, June
Health Phys.; 22_: 779-783
KEY WORDS: Americium complexes: Americium-241: Calcium complexes:
Chelates: Citrates: Curium complexes: Curium-242: DTPA: Injection:
Liver: Lungs: Plutonium complexes: Plutonium-239: Rats: Therapy:
Tissues: Zinc complexes.
ABSTRACT: The comparative effectiveness of Ca-DTPA and Zn-DTPA in
removing internally deposited 239Pu, 241^m ancj 242r,m was tested in the
rat. The radionuclides were administered in a citrate solution and treatment
with three chelate injections (1 mmol • kg~l • d"l) was begun 6 days
later. No essential differences were observed between the two chelates
tested. The data indicate that the removal of the isotopes from the liver
cannot be suitable criterion for the effectiveness of treatment in other soft
tissue organs. The liver isotope content was reduced to 10% of the control,
whereas the content of other organs, including bone, was never reduced to
less than 40% of the control. In liver and lung, the response to treatment
was different for 241Am and 242Cm as compared to 239Pu. There was no
such difference as far as other organs are concerned, (auth)
No. 164
Sanders, C. L.
Battelle Pacific Northwest Labs., Richland, Washington
Toxicology of Inhaled 2^2Cm02 in Rats. Progress report
1975, March
BNWL-1950(Pt. 1); pp. 35-37
105
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KEY WORDS: Biological radiation effects: Bone tissues: Curium oxides:
Curium-244: Deposition: Inhalation: Liver: Lung clearance: Lungs:
Neoplasms: Radioinduction: Radionuclide kinetics: Rats: Toxicity.
ABSTRACT: Preliminary results are reported from an experiment still in
progress. About 50% of initial alveolar deposition of 244Cm02 was
cleared from the lung during the first day and about 90% by 30 days after
exposure. 244r,m02 is more readily absorbed from the lung than plutonium
oxides, as evidenced by higher concentrations in bone and liver.
Adenocarcinoma is the predominant tumor type thus far observed in the lung.
Bone tumors were also observed, (auth)
No. 165
Rudnitskaya, E. I., and Yu. I. Moskalev
Moscow
Some Data on the Microdistribution and Pathological Anatomy of Curium-244
1975, ERDA-TR-51, pp. 95-101
KEY WORDS: Biological radiation effects: Curium chlorides: Curium-244:
Heart: Hematopoietic system: Intravenous injection: Kidneys: Liver:
Pathological changes: Radionuclide kinetics: Rats: Single intake:
Skeleton: Tissue distribution.
ABSTRACT: The work presents data on the microdistribution and
pathological anatomical changes in the organs and tissues of rats subjected
to a single intravenous injection of CmCl3 (pH 3.0) up to 200 days before
the beginning of the experiment. A dose of 0.2 to 0.1 pCi/g causes death of
the experimental animals with a picture of acute radiation sickness,
regardless of the period of death; some individuals survive up to 123 to 160
days after the beginning of the experiment at a dose of 0.1 yCi/g. Doses of
0.025, 0.01, 0.0025, and 0.001 yCi/g also produce specific changes, but less
pronounced. In the bone, liver, kidneys, and cardiac muscle, by the end of
the first day, aggregated particles of 244Qm are detected. The most severe
morphological changes develop in the hematogenic tissue contained in the bony
skeleton and in the liver, (tr-auth)
No. 166
Chipperfield, A. R., and D. M. Taylor
Department of Biophysics, Institute of Cancer Research, Sutton, Surry,
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United Kingdom
The Binding of Thorium(IV), Plutonium(IV), Americium(III) and Curium(III) to
the Constituents of Bovine Cortical Bone In Vitro
1972, July
Radia. Res.; 51_(1):15-30
KEY WORDS: Americium-241: Bone tissues: Curium-244: Glycoproteins:
In Vitro: pH value: Plutonium-239: Retention: Thorium-228: Uptake.
ABSTRACT: By means of a gel filtration technique it has been shown that
thorium(IV), plutonium(IV), americium(III) and curium(III) bind to five
glycoprotein fractions isolated from bovine cortical bone and to certain
other substances. The effects of p"H on the binding of plutonium to
poly-1-glutamic acid and to bone chondroitin sulfate and of curium to bone
sialoprotein and chondroitin sulfate-protein complex are described.
Plutonium, americium, and curium were found to bind to bone glycoproteins in
the presence of a 30-fold greater mass of bone mineral than glycoprotein.
Some experiments on the precipitation of calcium phosphate in vitro in the
presence of plutonium and americium are also presented. These observations
are discussed in the light of the hypothesis that certain actinide elements
are localized at bone surfaces by binding to glycoproteins. (auth)
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SUBJECT CATEGORY: Biological (Air Movement)
No. 167
Chapman, L. D., R. G. Cuddihy, J. R. Wayland, V. L. Dugan, and R. 0.
McClellan
Sandia Labs., Albuquerque, New Mexico
Environmental Dynamics of Toxic Releases and the Transport to Man
1975, April
Sand-75-5003; Conf-750418-1, 8 pp.
KEY WORDS: Air: Americium-241: Biological models: Curium-242:
Curium-244: Environment: Food Chains: Man: Plutonium-238: Plutonium-239:
Plutonium-240: Radioactive wastes: Radiobiological concentration:
Radionuclide migration: Toxicity: Transuranium elements.
ABSTRACT: A system dynamics model has been developed to explore the
long-term distribution of transuranics released into the environment. This
general model allows for assessment of the time-dependent distribution of
release including dispersal within the environment, integration within the
food chain, and transport to man of various effluents, (auth)
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SUBJECT CATEGORY: Biological (Human Inhalation)
No. 168
Barr, N. F.
Div. of Biomedical and Environmental Research, Washington, D.C.
Assessment of Potential Health Consequences of Transuranium Elements
1974, May
STI/Pub-375; Conf-740529, pp. 451-462
KEY WORDS: Aerosols: Americiu'm isotopes: Americium-241: Biological
radiation effects: Curium isotopes: Electric power: Fuel cycle: Health
hazards: Ingestion: Inhalation: LMFBR type reactors: Man: Particles:
Plutonium isotopes: Radiation doses: Toxicity: Transuranium elements.
ABSTRACT: The results are presented of a study to provide quantitative
estimates, per unit of electrical power generated, of potential consequences
to human health from inhaled or ingested transuranium elements released
during the generation of electricity by the liquid metal fast breeder reactor
(LMFBR) fuel cycle. Soon after release, direct inhalation of downward
descending airborne particles is the dominant route of entry of transuranic
elements into man. The fraction of material entering man in this way is
estimated to be 4 x 10~6. A comparable fraction enters man through
inhalation of material resuspended into the atmosphere after deposition.
Estimates for the fraction of released material that enters man through
ingestion processes from the time of release to complete decay of the
activity are made for the most significant radioisotopes of plutonium,
americium and curium. 241^ js the largest contributor to dose by this
pathway. Health effects estimates based on current metabolic data, ICRP dose
models and the report of the Committee on Biological Effects of Ionizing
Radiation of the U.S. National Academy of Sciences, when combined with these
pathway analyses, indicate that there are unlikely to be more than about
10"3 potential health effects for each 1000-megawatt electric year of power
generated, (auth)
No. 169
Barr, N. F-
ERDA, Health Safety Lab., New York
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Quantitative Health Estimates of Transuranic Releases
1975, April
HASL-211, 1.5-1.17
KEY WORDS: Air: Americium isotopes: Americium-241: Biological
radiation effects: Curium: Isotopes: Decay: Fuel cycle: Health hazards:
Human populations: Ingestion: Inhalation: LMFBR type reactors: Particles:
Plutonium isotopes: Radiation doses: Radioactive wastes: Transuranium
elements.
ABSTRACT: Estimates are presented of potential consequences to human
health from transuranium elements released during the generation of
electricity by the liquid metal fast breeder reactor (LMFBR) fuel cycle.
Direct inhalation of downward descending airborne particles is the dominant
route of entry of transuranic elements into man. The fraction of material
entering man in this way is estimated to 4 x 10~6. This appears to be an
upper limit for the fraction which might enter man through inhalation of
material resuspended into the atmosphere after deposition. Upper estimates
for the fraction of released material that enters man through ingestion from
the time of release to complete decay of the activity are made for the most
significant radioisotopes of plutonium, americium, and curium. 241/\m js
the largest contributor to dose by this pathway. Health effects estimates
based on current metabolic data, ICRP dose models, and the report of the
committee on Biological Effects of Ionizing Radiaton of the U.S. National
Academy of Sciences, when combined with these pathway analyses, indicate that
there are unlikely to be more than about 10~3 potential health effects for
each 1000-megawatt electric year of power generated, (auth)
No. 170
Bernard, S. R., and J. W. Poston
Oak Ridge National Lab., Tennessee
Estimation of Dose Commitment from an Accidental Intake of 244Cm
1976, February
Conf-760202-13, 14 pp.
KEY WORDS: Body burden: Curium-244: Dose commitments: DTPA:
Excretion: Feces: Inhalation: Internal irradiation: Liver: Lungs:
Measuring methods: Personnel: Personnel dosimetry: Radiation dose
distributions: Radiation doses: Radiometric analysis: Radionuclide
kinetics: Response modifying factors: Retention functions: Sampling:
Skeleton: Tissue distribution: Urine; Whole-body counting.
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ABSTRACT: Four employees at the Oak Ridge National Laboratory
experienced an intake by inhalation of 244Cm as a result of an accidental
release of this nuclide. Urine and fecal samples were obtained and were
analyzed in the Bioassay Laboratory at ORNL. Also, chest counts were made
with the ORNL whole-body counter. Ca-DTPA mists were inhaled within hours
after the intake. These data together with data on the inhalation of 244Cm
by a dog were used to obtain a 40-year dose commitment to lungs, skeleton,
and liver. The 50-year dose commitment to skeleton for two of the employees
was estimated to be about 170 rem. The estimation methods used for dose
commitment together with the values' for other organs obtained are presented
and discussed, (auth)
No. 171
Parkinson, W. W., L. C. Henley, R. E. Goans, and W. M. Good
Oak Ridge National Lab., Tennessee
Evaluation of Two cases of 244Cm Inhalation
1976, February
Conf-760202-19, 7 pp.
KEY WORDS: Body burden: Curium-244: Dose commitments: Excretion:
Feces: Inhalation: Internal irradiation: Measuring methods: Personnel:
Personnel dosimetry: Radiation dose distributions: Radiation doses:
Radiometric analysis: Retention functions: Sampling: Urine: Whole-body
counting.
ABSTRACT: Chest and systemic burdens were estimated for two employees
who inhaled largely soluble compounds of 244Cm. Chest burdens by
whole-body counting were: Case A, 28 nCi; Case B, 34 nCi. The urinary
excretion of the employees appeared to conform to a series of exponentials
similar to those reported for blood and whole-body retention of Am in
baboons. Accordingly, retention functions composed of a series of
exponentials having 4-, 12-, to 17-, and 72-day half-times were derived from
urinary excretion and used to calculate body burdens; Case A was 7 nCi and
Case B was 16 nCi. Cumulative fecal excretion by Case B was some 20 times
that by Case A (63 nCi vs. 3.2) probably due to differences in deposition in
the respiratory tract. Calculated organ doses for the first year were
approximately 20 percent of recommended maximum, (auth)
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No. 172
Stather, J. W., F. E. H. Crawley, D. S. Popplewell, G. N. Stradling, J.
Grightwell, B. L. Loveless, L. Watts, and R. J. Purrot
National Radiological Protection Board, Harwell, United Kingdom
Radiological Protection of People Exposed to Plutonium: Current Research at
the National Radiological Protection Board
1974, October
NRPB-R-31; 127 pp.
KEY WORDS: Americium-241: Chromosomal aberrations: Clearance:
Curium-242: Lavage: Lungs: Lymphocytes: Man: Plutonium: Plutonium-238:
Plutonium-239: Quantitative chemical analysis: Radiation protection:
Radio-induction: Radionuclide kinetics: Rats: Research programs:
Respiratory system: Tissue distribution: United Kingdom organizations:
Urine.
ABSTRACT: The report consists of a general foreword on the current
research program at the NRPB, followed by individual contributions on the
following topics: The effect of chemical form on the tissue distribution and
excretion of plutonium-239 following its deposition in the respiratory system
of rodents; comparative studies on the clearance of plutonium-238,
plutonium-239, americium-241, and curium-242 from the respiratory system of
the rat; chemistry of plutonium incorporated in humans; a rapid method for
the determination of plutonium in urine by ultra filtrations; the efficiency
of bronchopulmonary lavage as a therapeutic procedure for removing insoluble
radioactive particles from the lung; studies of the removal of intracellular
plutonium; analysis of data on the clearance of insoluble compounds of
plutonium in the lung; chromosome aberrations in lymphocytes after plutonium
intake by humans. (UK)
No. 173
Strom, P. 0., and E. C. Watson
Battelle Pacific Northwest Labs., Richland, Washington
Calculated Doses from Inhaled Transuranium Radionuclides and Potential Risk
Equivalance to Whole-Body Radiation.
1975, November
BNWL-SA-5588; Conf-751105-16; SM-199/144, 34 pp.
KEY WORDS: Americium-241: Americium-242: Americium-243:
Americium-244: Body: Bone Tissues: Comparative evaluations: Computer
calculations: Computer codes: Curium-242: Curium-243: Curium-244:
Curium-246: D codes: Dose commitments: Gastrointestinal tract:
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Inhalation: Internal irradiation: Kidneys: Liver: Lungs: Man:
Neoplasms: Plutonium-237: Plutonium-238: Plutonium-239: Plutonium-240:
Plutonium-241: Plutonium-242: Plutonium-243: Plutonium-244: Radiation
dose distributions: Radiation doses: Radiation hazards: Radionuclide
kinetics: Tissue distribution: Whole-body irradiation.
ABSTRACT: The distributon of radiation dose commitments within the
body that can result from the lung deposition of a number of transuranic
radionuclides (237PUj 238Pu> 239Pu> 240PUj 241Pllj 242Pu> 243Pu> 241^,
242Am> 243^, 244^, 242Cm> 243Crr,5 244Cm> and 246Cm) was calculated. The
variables that influence these organ dose commitments include the mobility of
the particle or its dissolution products within the body, the radiation
characteristics of the inhaled radionuclides and their progeny, and the size
of the particles inhaled. In the calculation of organ dose commitments for
whole-body, lungs, liver, bone tissues, kidneys and gastrointestinal tract
from the inhalation of transuranium radionuclides, physical characteristics
of importance are the dimensions of the particle, its aerodynamic properties,
and its density. For particles within the respirable size range, a useful
description is provided by the activity median aerodynamic diameter. Dose
commitments resulting from acute inhalation of plutonium, americium, and
curium nuclides relative to the activity median aerodynamic diameter (AMAD)
were calculated using the computer program DACRIN. Deposition efficiencies
were estimated for several regions of the respiratory tract as a function of
the AMAD. These locations within the respiratory tract are described as the
nasopharyngeal, the tracheobronchial, and the pulmonary regions. The
deposition, migration, and retention of particles introduced into the
respiratory tract are represented by descriptive mathematical models of these
phenomena within the respiratory system. Estimates of the risk of excess
deaths from cancer due to whole-body radiation doses are included in the
calculations to provide an estimate of cancer death risks associated with the
inhalation of transuranic compounds. These results are then equated to those
from whole-body radiation doses. (CH)
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SUBJECT CATEGORY: Measurement
No. 174
Gavron, A., H. C. Britt, E. Konecny, J. Weber, and J. B. Wilhelmy
Los Alamos Scientific Laboratory, Univ. of California, Los Alamos, New Mexico
Measurement and Interpretation of Gamman Gammaf for Actinide Nuclei
1975, March
Phys. Rev. Lett.; 34(13):827-830
KEY WORDS: Americium isotopes:" Curium isotopes: Energy dependence:
Fission: Helium-3 reactions: MeV range 10-100: Neptunium isotopes:
Nuclear reaction kinetics: Plutonium isotopes: Probability: Protactinium
isotopes: Statistical models: Uranium isotopes: Deuterons: Stripping:
Tritons.
ABSTRACT: The (3He,df) and (3He,tf) reactions were used to measure
fission probabilities from threshold up to ~ 12 MeV of excitation energy for
a series of actinide nuclei. The data were fitted over the whole range of
nuclei and excitation energies with a microscopic model which does not
contain an arbitrary normalization for Fn/Ff. The fits indicate that for
most actinide nuclei fission proceeds through a first saddle point that is
not axially symmetric, (auth)
No. 175
Jaffey, A. H., and J. L. Lerner
Some Measurement of Prompt-Neutron Fission Yield (vp) in Thermal-Neutron
Fission of 232U, 238Pu> 241Pu> 241Anis 242mAm> 243Cj 245Cm> and in
Spontaneous Fission of 244Cm
ANL-7625, Argonne National Lab., 111. 54 pp.
KEY WORDS: Prompt neutrons: Fission yield: Fission: Neutron beams:
Thermal neutrons: Americium-241: Americium-242: Curium-243: Curium-244:
Curium-245: PIutonium-238: Plutonium-241: Uranium-232: Curium-244:
Spontaneous fission.
ABSTRACT: The prompt-neutron fission yield (vp) has been measured
in thermal-neutron fission of 232U, 238Pu, 241Am, 242mAm, 243Cm,
249cm, and in the spontaneous fission of 244Cm. These have been measured
by comparison with vp-values of the standards 233U, 23^U, 23^pu, and
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"<-Cf. A coincidence method was used with fission fragments detected in an
ionization chamber at close to 100% efficiency and with fission neutrons
detected using four symmetrically placed ZnS(Ag) methyl methacrylate discs
(Hornyak buttons). A small variation of neutron-detection efficiency with
fission-neutron spectrum differences was calibrated with the four standard
nuclides. The measured values vp are: 237U, 3.130 +_ 0.060, 238Pu,
2.895+0.027, 241pUj 2.874+0.015, 241Am> 3.219+0.038, 242mAm,
3.264 +_ 0.024, 243Cm> 3>430 ±0.047, 245Cm> 3>832 + Q.034, 244Cm> 2.692
+ 0.024.
No. 176
Yates, S. W., I. Ahmad, A. M. Friedman, F. J. Lynch, and R. E. Holland
Argonne National Laboratory, Argonne, Illinois
Lifetimes of the 1/2 +(631) Yields, 5/2 + (622) E2 Transition in Some
Actinide Nuclei
1975, February
Phys. Rev., C.; 11(2):599-606
KEY WORDS: Curium-243: Curium-245: Energy levels: Energy-level
transitions: Lifetime: Nilsson-Mottelson model: Pairing interactions:
Plutonium-241: Plutonium-243: Uranium-239: Gamma spectra: Plutonium-242:
Protons: Stripping.
ABSTRACT: Lifetimes of the E2 transitions from the 1/2 + [631] state to
the 5/2 + [622] state have been measured in several actinide nuclei using
pulsed beam and delayed coincidence techniques. The 1/2 + [631] level was
excited in 239y and 243pu by the (d,p) reaction and in 241pu by the
(d,t) reaction, and the subsequent Y-ray decay to the 5/2 + [622] level was
observed between beam pulses. The corresponding E2 transitions were observed
in 243Cm and 245Cm from the radioactive decay of 243Bk and 245Bk,
respectively, and the lifetimes were determined from electron-photon delayed
coincidence experiments. The half-lives from these measurements are as
follows: 239U(0.78 + 0.04 ys), 241Pu (0.88 + 0.05 ys); 243Pu (0.331
0.03 ys); 243Cm (1.08+0.03 Ps); and 245Cm (0.29+0.02 ys). Comparisons
are made between the experimental transition probabilities and theoretical
estimates. The differences between the transition rates in these nuclei are
understood when pairing interactions are taken into account, (auth)
115
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No. 177
Zhuravlev, K. D., Yu. S. Zamyatnin, and N. I. Kroshkin
Gosudarstvennyj Komitet Po Ispol'zovaniyu Atomnoj Ehnergii USSR
Energy Spectra and Mean Value Anti Nu of Prompt Neutrons of the Curium
Isotope Fission
1974, March
INIS-MF-1698; Conf-740376-P4, pp. 57-62
KEY WORDS: Curium-243: Curium-244: Curium-245: Curium-246:
Curium-247: Curium-248: Energy spectra: Neutron reactions: Prompt
neutrons: Spontaneous fission: Thermal fission.
ABSTRACT: Results are presente.d on measurement of the average number v
and the spectra of prompt fission neutrons from curium isotopes. The average
spectral energies E during spontaneous fission of ^-^Cm, ^°Cm, and
248Cm, and the fission of 243Cm, 245Cm, and 247Cm by thermal neutrons
were found to be respectively 2.07 +_ 0.05, 2.09 +_ 0.06, 2.15 +_ 0.06, 2.15 +_
0.06, 2.25 +_ 0.08, and 2.20 +_ 0.06 MeV. The average number v of neutrons
from these nuclei were respectively: 2.680 +_ 0.027, 2.927 ±0.027, 3.173 +_
0.022, 3.39 _+ 0.14, 3.80 +_ 0.16, and 3.79 +_ 0.15. The dependence of E and v
as a function of various parameters of the fissioning nucleus is discussed.
(tr-SJR)
No. 178
Boldeman, J. W.
Gosudarstvennyj Komitet Po Ispol'zovaniyu Atomnoj Ehnergii USSR
Recent Relative Nu-Bar Measurements
1974, March
INIS-MF-1698; Conf-740376-P4, pp. 114-120
KEY WORDS: Curium-244: Curium-246: Plutonium-240: Plutonium-242:
Prompt neutrons: Spontaneous fission.
ABSTRACT: Measurements were made of the value of vp for 244Qm an(j
246Cm relative to vp = 3.724 for 252Cf using a large liquid scintillator.
ts
were re-examined, (tr-auth)
Previous measurements of vp for 240pu and 242pu relative to
No. 179
Blaise, A.
CEN, Grenoble, France
116
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Regent Work in Actinides at Grenoble
1974, June
ARER-R-7961; Conf-7406103, pp. 4-5
KEY WORDS: Actinides: Americium: Arsenides: Curium: Magnetic
properties: Neptunium: Neptunium compounds: Neutron diffraction:
Plutonium compounds: Specific heat: Tellurides: Uranium compounds.
ABSTRACT: A summary of results in magnetic measurements, specific heat
and neutron diffraction studies is given for Np, Am, Cm, and Np and Pu
compounds of the type AnX, AnX2, and AnX3- (MCG)
No. 180
Dunlap, B. D., and G. M. Kalvius
Argonne National Lab., Argonne, Illinois
1974
Academic Press, Vol. 1, pp. 237-301
KEY WORDS: Actinium: Americium: Curium: Hyperfine structure:
Moessbauer effect: Neptunium: Plutonium: Protactinium: Thorium: Uranium.
ABSTRACT: Hyperfine-interacton studies are reviewed, and the solid-state
information obtained by such measurements is given. The three techniques
considered are: nuclear orientation, perturbed angular correlation, and
Moessbauer effect or nuclear Y resonance. (LK)
No. 181
Fuger, J., J. Reul, and W. Mulier
Liege University
New Determination of the Enthalpy of Solution of Curium Metal and the
Enthalpies of Formation of Cm3+(AQ) and CMO_3(S)
1975, May
Inorg. Nucl. Chem. Lett; Vol. 11, No. 5, 265-275
KEY WORDS: Cations: Curium: Curium chlorides: Formation heat:
Hydrochloric acid: Solution heat.
ABSTRACT: The enthalpy of solution of curium metal (dhcp structure) in
1M HC1 has been measured at 298.15 _+ 0.1°K, giving a value of -614.5 +_ 4.5 kJ
mol'l. From this value, the standard enthalpy of formation of Cm3+(aq)
is deduced as -615 _+ 5 kJ mol'l and, using reasonable entropy estimates,
the standard potential of the Cm(0)/Cm(III) couple is calculated to be 2.07 +_
117
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0.03 V. Calculation also yields a value of -971 +_ 6 kJ mol"1 for the
standard enthalpy of formation of CmClsCs) at 298°K. (auth)
No. 182
Fujita, D. K., T. C. Parsons, N. Edelstein, M. Noe, and J. R. Peterson
California University, Lawrence Berkeley Lab., Berkeley, California
1975, September
LBL-4076; Conf-750913-12, 9 pp.
KEY WORDS: Californium-249: Curium-244: FCC Lattices: Magnetic
susceptibility: Metals.
ABSTRACT: The first magnetic susceptibility measurements made on the
expanded fee phase of 249Qf metal are reported. Further measurements are
needed on other Cf metal phases. Another measurement of the magnetic
susceptibility of 244cm metal in a limited temperature range has been
reported. The result does not agree with previously reported values.
Further work is continuing on the synthesis of 244^ metal and 248r,m
metal and magnetic measurements on these samples, (auth)
No. 183
Goans, R. E.
Oak Ridge National Lab., Tennessee
Detection of Internally Deposited Actinides. Part II. Statistical
Techniques and Risk Analysis
1976, February
Conf-760202-4, 7 pp.
KEY WORDS: Americium: Computers: Contamination: Curium-244:
Environmental effects: Gadolinium-153: Lungs: Personnel: Plutonium-239:
Radiation detection: Radiation doses: Radiation hazards: Radiation
protection: Spectra: Statistics: Strontium-90: Uranium-233.
ABSTRACT: Since a considerable number of workers at Oak Ridge National
Laboratory work with compounds of the transuranic elements, computer
techniques have been developed to evaluate Phoswich spectra in order to
determine lung burdens following accidental inhalation of 239pUj 241/\mj
244cm or other isotopes. Two unfolding methods which have been found
useful in the analysis of such cases are presented and discussed. These
techniques have been used successfully to detect low levels of
118
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241Am, 244Cm, 233ut 90sPj and 153Gd in contaminated workers; but because of
the current importance of 239pU) emphasis is placed on detection of that
isotope in the presence of 241/\m an(j natural human background. In the
health physics tradition of emphasizing benefit vs. risk, we also analyze
uncertainties inherent in external counting of the actinides from the
viewpoint of statistical risk analysis and derive decision criteria which are
useful in determining whether various radioactive species have, in fact, been
detected. These criteria are somewhat different from those encountered using
traditional counting statistics and derive from the realization that some
errors will always be made in scann-ing large numbers of radiation workers.
The optimum decision strategy for the determination of lung burden is,
therefore, one which minimizes the long-term risk of error. The usefulness
of this approach to whole body counting will be discussed and analyzed.
(auth)
119
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SUBJECT CATEGORY: Dosimetry
No. 184
International Atomic Energy Agency, Vienna, Austria
Reference Methods for Marine Radioactivity Studies II
1975, July
STI DOC-10 169, 244 pp.
KEY WORDS: Americium-241: Aquatic Ecosystems: Curium-244: Iodine-131:
Isometric nuclei: Marine disposal: PIutonium-238: Plutonium-239:
Quantitative chemical analysis: Radiation monitoring: Radioactive
effluents: Radiometric analysis: Radionuclide migration: Ruthenium-106:
Sample preparation: Sampling: Seas: Seawater: Sediments: Silver-110:
Zirconium-95.
ABSTRACT: Methods for monitoring certain radionuclides released to the
marine environment in effluents from the nuclear industry are discussed.
Analytical methods for the identification of nuclides of the transuranic
elements Ru, Zr, Ag, and I in seawater samples are included. (CH)
No. 185
Bemis, C. E., Jr., R. E. Goans, W. M. Good, and G. G. Warner
Oak Ridge National Lab., Tennessee
Detection of Internally Deposited Actinides. Part IV. Preliminary
Considerations in the Use of Large, Planar Intrinsic GE Detectors
1976, February
Conf-760202-20, 4 pp.
KEY WORDS: Actinides: Americium-241: Californium-250: Curium-244:
Curium-246: Geiger-Mueller counters: Internal irradiation: Performance
testing: Personnel: Personnel dosimetry: PIutonium-238: Plutonium-239:
Plutonium-240: Plutonium-242: Radiation doses: Whole-body counting.
ABSTRACT: Many inherent advantages are apparent in the use of large
planar Ge detectors for the detection, identification, and quantitative
assessment of internally deposited actinide nuclides (238pu> 239pU)
240PU} 242Pu> 241A[T1} 244Cm> 246Cm> and 250Cf). The superior energy
resolution, in contrast to Phoswich-type scintillation detectors, permits
isotopic identifications to be made and reduces ambiguities introduced by
natural and human background effects. Preliminary studies indicate that
120
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a 10-cm2 x 1.2-cm GE detector is comparable in detection sensitivity to
that of one 125-cm^ Phoswich detector. Some preliminary considerations and
evaluations of photon transport studies based on Monte Carlo modeling and
measurements of absolute L-series x-ray yields in the decay of several
actinide nuclides are presented, (auth)
121
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AUTHOR INDEX
ABDEL-LATIF BILAL, B. 137
AHMAD, I. 109
ALEKSANDROVA, Z.A. 110
ALLER, P.P. 41
ARGONNE NATIONAL LABORATORY 7, 111
ATOMIC INTERNATIONAL DIVISION 26
BAIR, W.J. 152, 153
BAKER, K.R. 104, 115
BARR, N.F. 168, 169
BEMIS, C.E. 185
BERNARD, S.R. 170
BIBLER, N.E. 120
BLAISE, A. 179
BOLDEMAN, J.W. 178
BOND, W.D. 61
BOWEN, V.T. 1
BROWN, P.E. 50
BURNES, J.H. 119
CAPGRAS, A. 96
CARNALL, W.T. 118
CARNEY, H.C. 28, 51
CASAGRANDE, R.D. 27
CHAPMAN, L.D. 167
CHARKIN, O.P. 81
CHARVILLAT, J.P. 82
CHIARIZIA, R. 70
CHIPPERFIELD, A.R. 166
CHMUTOVA, M.K. 128, 129
CHUVELEVA, E.A. 121, 122
CLAIRBORNE, H.C. 62
CRAIG, D.K. 155
CRAIG, D.P. 148
CROUCH, E.A.C. 11
DABBS, J.W.T. 105
DAMIEN, D. 78
DAVID, F. 71, 90, 91
DELCHEV, Ya.I. 22
DELLE SITE, A. 146
DISTEFANO, J.R. 32
DOUGHERTY, J.H. 149
DUNLAP, B.D. 180
EAKINS, J.D. 147
EBERLE, S.H. 52
EGGERS, P.E. 33
ELESIN, A.A. 76
ENVIRONMENTAL PROTECTION AGENCY 2
ERDMANN, R.C. 39
ERSKINE, J.R. 85
FINSTERWALDER, L. 53
FOOS, J. 130, 142
FREEMAN, A.J. 4
FUGER, J. 181
FUJITA, D.K. 182
GAVRON, A. 174
GEDEONOV, L.I. 124
GIRARDI, F. 54
GOANS, R.E. 183
GODBEE, H.W. 63
GOURISSE, D. 55
GUSEVA, L.I. 144
HAIDVOGEL, N. 143
HANSEN, J.E. 30
HARBOUR, R. M. 47
HARRAR, J.E. 5, 6
HITTMAN ASSOCIATES, INC. 57
HOFF, R.W. 9
HOLMAN, R. 34
HOOSHYAR, M.A. 86
IKEDA, N. 145
INTERNATIONAL ATOMIC ENERGY AGENCY
184
JAFFEY, A.H. 175
JONES, I.R. 29
KERRIGAN, W.J. 116
KILLEN, R.E. 31
KING, L.J. 21
122
-------
KOROTKIN, Yu.S. 66, 67, 69
KOTRAPPA, P. 156
LAFUMA, J. 150
LAMB, E. 12, 13, 14, 15, 16, 17, 18
LEBEDEV, I.A. 140
LIBERMAN, A.R. 40
LISIN, S.K. 123
LIUKKONEN, E. 107
LLOYD, R.D. 157, 158
LORCH, E.A. 97
LOUGHEED, R. 80
LYLE, S.J. 141
MADHVANATH, U. 154
MARTIN MARIETTA CORPORATION 35
MARTINOT, L. 83
MARTINOV, M.S. 89
MASON, G.W. 139
MAYS, C.W. 159
MCDONNELL, W.R. ioe
MCELROY, J.L. 56
McGOWAN, F.K. 127
McHARGUE, C.J. 8
MOSKALEV, Yu.I. 160
MOSLEY, W.C. 48
MYASOEDOV, B.F- 65, 131
SAMHOUN, K. 108
SANDERS, C.L. 151, 164
SCHRAMM, D.N. 99
SCHUMANN, F.A. 38
SEIDEL, A. 163
SHAFIEV, A.I. 138
SHAW, H.P. 10
SHEVCHENKO, V.B. 58
SILL, C.W. 100
SOLOV'EVA, Z.I. 88
STATHER, J.W. 172
STEPHANOV, A.V. 75
STEVENSON, J.N. 74
STROM, P.O. 173
SULLIVAN, M.F. 162
SZEGLOWSKI, Z. 135
TELEDYNE ISOTOPE, ENERGY SYSTEMS
DIVISION 42, 43, 44, 45
THOMAS, C.W. 24
THOMPSON, R.C. 114, 117
TRET'YAKOV, Yu.D. 73
TSAMERYAN, I.I. 77
TYUFYAKOV, N.D. 112
UENO, K. 136
UMEZAWA, H. 132
NENOT, J.C. 161
NUGENT, L.J. 79
OAK RIDGE NATIONAL LABORATORY 49,
60, 64
OSMEYER, W.E. 37
OTTINGER, C.L. 19, 20
PARKINSON, W.W. 171
PASTO, A.E. 84
PIGFORD, T.H. 23
PORTER, F.T. 95
PYPER, D.M. 113
RAAB, B. 25, 36
RAMANIAH, M.V. 125
RUDNITSKAYA, E.I. 165
RUDRAN, K. 98
WARD, J.W. 68
WATSON, R.L. 101
WHEELWRIGHT, E.J. 59
WILLIAMS, E.W. 46
YAMAJI, S. 87
YATES, S.W. 94, 176
YODER, R.E. JR. 3
ZACHARIASEN, W.H. 72
ZAITSEV, A.A. 133, 134
ZAKHAROV, E.A. 102
ZALUTSKY, M.R. 92, 93, 103, 126
ZHURAVLEV, K.D. 177
123
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KEYWORD INDEX
ABSORPTION 8
ABSORPTION SPECTRA 118
ABSORPTION SPECTROSCOPY 120
ACCURACY 102
ACETIC ACID 77
ACTINIDE COMPOUNDS 84
ACTINIDE NUCLEI 9
ACTINIDES 139, 179, 185
ACTINIUM 4, 71, 81, 90, 91, 130, "
141, 142, 180
ACTINIUM BROMIDES 72
ACTINIUM CHLORIDES 72
ACTINIUM COMPOUNDS 72, 79
ACTINIUM FLUORIDES 72
ACTINIUM OXIDES 72
ACTINIUM-227 48
ADSORBENTS 138
ADSORPTION 147
AEROSOLS 156, 168
AGE DEPENDENCE 162
AIR 53, 167, 169
ALCOHOLS 143
ALKYL RADICALS 139
ALLOYS 8
ALLOY - TZM 12, 13, 35
ALPHA BEAMS 106
ALPHA DECAY 7, 92, 101, 104, 115, 116
ALPHA PARTICLES 88, 105, 120, 147,
152, 154
ALPHA REACTIONS 107, 109, 123, 127
ALPHA SOURCES 105, 106, 149, 151, 153
ALPHA SPECTRA 52
ALPHA SPECTROSCOPY 100, 124
ALUMINUM 8
ALUMINUM ALLOYS 8
ALUMINUM OXIDES 19, 56
AMERICIUM 4, 53, 54, 55, 58, 59, 60,
61, 62, 64, 66, 67, 70, 71, 81, 90,
91, 95, 98, 102, 108, 111, 113, 121,
122, 124, 125, 128, 129, 130, 131,
132, 133, 134, 135, 136, 137, 138,
139, 141, 142, 143, 144, 145, 146,
147, 179, 180, 183
AMERICIUM BROMIDES 72
AMERICIUM CHLORIDES 72
AMERICIUM COMPLEXES 76, 129, 134, 163
AMERICIUM COMPOUNDS 66, 70, 72, 75,
79, 82
AMERICIUM FLUORIDES 72
AMERICIUM IONS 107
AMERICIUM ISOTOPES 23, 24, 168, 169,
174
AMERICIUM NITRATES 143
AMERICIUM OXIDES 72, 107, 136, 148
AMERICIUM PHOSPHIDES 82
AMERICIUM SULFATES 143
AMERICIUM-237 109
AMERICIUM-241 1, 2, 7, 10, 11, 12,
48, 52, 55, 77, 95, 97, 100, 101,
107, 124, 129, 143, 148, 150, 152,
153, 155, 156, 158, 159, 161, 162,
163, 166, 167, 168, 169, 172, 173,
175, 184, 185
AMERICIUM-242 1, 10, 52, 107, 173,
175
AMERICIUM-243 1, 10, 21, 48, 49, 52,
55, 100, 173
AMERICIUM-244 52, 173
AMMONIUM COMPOUNDS 98, 144
ANGULAR CORRELATION 93, 103
ANGULAR DISTRIBUTION 85
ANIONS 129, 145
ANTIMONY COMPOUNDS 82
ANTIMONY-127 123
ANTIMONY-129 123
AQUATIC ECOSYSTEMS 184
AQUEOUS SOLUTIONS 58, 65, 79, 100,
108, 118, 124, 129, 137, 143
AROMATICS 60
ARSENIDES 179
AUGER EFFECT 95
AUTORADIOGRAPHY 143
AVAILABILITY 50, 51
BAND THEORY 4
BARNWELL FUEL PROCESSING PLANT 51,
59
BCRON 97
BEAGLES 148, 149, 155, 156, 157, 158,
159
BENZENE 124
124
-------
BERKELIUM 4, 6, 71, 81, 90, 91, 108,
111, 128, 131, 133, 134, 138, 140,
141, 142
BERKELIUM BROMIDES 72, 119
BERKELIUM CHLORIDES 72
BERKELIUM COMPLEXES 134
BERKELIUM COMPOUNDS 72, 79
BERKELIUM FLUORIDES 72
BERKELIUM OXIDES 72
BERKELIUM-249 2, 9. 21, 49, 74, 85,
119, 140
BERYLLIUM 19, 96, 97, 112
BERYLLIUM OXIDES 73
BETA-MINUS DECAY 9
BETA SPECTROSCOPY 124
BIBLIOGRAPHIES 55
BINDING ENERGY 72
BIOASSAY 98, 146
BIOLOGICAL HALF-LIFE 148
BIOLOGICAL MODELS 167
BIOLOGICAL RADIATION EFFECTS 2, 149,
150, 151, 152, 153, 164, 165, 168,
169
BISMUTH 135
BLOOD FORMATION 149
BODY 173
BODY BURDEN 2, 152, 170, 171
BOND LENGTHS 72, 119
BONE TISSUE 149, 164, 166, 173
BORON 141
BOUNDARY CONDITIONS 89
BRANCHING RATIO 95
BRAYTON CYCLE 26, 31
BROMINE 6
BUTANOLS 69
CADMIUM 141
CADMIUM-115 123
CALCINATION 56
CALCIUM COMPLEXES 163
CALIBRATION STANDARDS 100
CALIFORNIUM 6, 70, 81, 89, 90, 91,
108, 111, 130, 131, 133, 134, 136,
141, 142, 144
CALIFORNIUM BROMIDES 72, 119
CALIFORNIUM CHLORIDES 72
CALIFORNIUM COMPLEXES 129, 134
CALIFORNIUM COMPOUNDS 70, 72, 79
CALIFORNIUM FLUORIDES 72, 80
CALIFORNIUM ISOTOPES 87, 88
CALIFORNIUM OXIDES 72
CALIFORNIUM-244 10
CALIFORNIUM-245 86
CALIFORNIUM-247 158
CALIFORNIUM-248 22
CALIFORNIUM-249 7, 11, 47, 119, 159,
182
CALIFORNIUM-250 129, 185
CALIFORNIUM-251 10
CALIFORNIUM-252 2, 3, 21, 48, 49, 97,
100, 101, 105, 110, 112, 120, 123,
128, 129, 158, 159
CALORIMETERS 13
CALORIMETRY 116
CAPSULES 12, 14, 15, 16, 17, 18, 19,
20, 30, 32, 35
CAPTURE 52
CARBON 19
CARBON-13 97
CARBON-14 24
CARBOXYLIC ACIDS 76
CARCINOGENESIS 151, 152
CARCINOMAS 150
CARDIAC PACEMAKERS 52
CATIONS 66, 70, 79, 83, 118, 132,
138, 142, 181
CERAMICS 8
CERIUM 55, 66, 70, 81, 124, 132,
135, 138, 140, 141, 142, 144
CERIUM COMPOUNDS 70, 79, 120
CERIUM IONS 113
CERIUM OXIDES 73
CERIUM-141 123
CERIUM-143 123
CERIUM-144 55, 123 161
CESIUM 55, 56, 141
CESIUM-134 53
CESIUM-135 24
CESIUM-137 12, 53, 55, 63
CHARGED-PARTICLE TRANSPORT 107
CHELATES 163
CHEMICAL ANALYSIS 102, 124, 141, 146
CHEMICAL BONDS 72
CHEMICAL COMPOSITION 73, 113
CHEMICAL PREPARATION 69. 74, 76, 78
82, 138
CHEMICAL PROPERTIES 135, 148
CHEMICAL RADIATION EFFECTS 120
CHEMICAL REACTION KINETICS 60, 66,
69, 73, 75, 76, 135, 141, 142
CHEMICAL REACTIONS 19, 75
CHEMICAL VAPOR DEPOSITION 30
CHEMISTRY 73
125
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CHLORATES 118
CHLORINE 6
CHLOROFORM 135
CHROMATOGRAPHY 66, 111, 121, 122
CHROMIUM 8
CHROMIUM OXIDES 56
CHROMOSOMAL ABERRATIONS 172
CHRONIC INTAKE 160
CHRONIC IRRADIATION 151, 152
CITRATES 157, 163
CLEARANCE 172
COAL 7
COBALT-60 13, 24, 39, 48
COINCIDENCE METHODS 104, 115, 126
COINCIDENCE SPECTROMETRY 95
COLLECTIVE MODEL 117
COMMUNICATIONS 42, 43, 44, 45
COMPARATIVE EVALUATIONS 9, 25, 33,
173
COMPATIBILITY 12, 13, 15, 16, 17,
18, 19, 20, 32
COMPLEXES 121, 129, 163
COMPOSITE MATERIALS 8
COMPOUND-NUCLEUS REACTIONS 107, 109
COMPUTER CALCULATIONS 173
COMPUTER CODES 173
COMPUTERS 183
CONTAMINATION 154, 183
CONTAINERS 106
CONTROL 3
CONTROL CRITICALITY 10
CONTROL SYSTEMS 36
COORDINATION VALENCES 119
COPPER ALLOYS 8
CORROSION 8, 14, 16
COSMOCHEMISTRY 99
COST 25, 28, 34, 37, 50, 51
COSTER-KRONIG TRANSITIONS 103, 104,
126
COULOMB EXCITATION 114, 127
CREEP 8, 17, 18
CRITICALITY 19
CROSS SECTIONS 52, 94, 105, 117
CRYSTAL LATTICES 78, 119
CRYSTALS 73
CRYSTAL STRUCTURE 8, 78, 82
CURIUM 4, 5, 6, 53, 54, 55, 56, 58,
59, 60, 61, 62, 64, 65, 67, 70, 71,
81, 83, 89, 90, 91, 98, 101, 102,
108, 111, 113, 121, 122, 124, 125,
126, 128, 129, 130, 131, 132, 133,
134, 135, 136, 137, 138, 139, 141,
142, 143, 144, 145, 146, 147, 163,
169, 179, 180, 181
CURIUM ARSENIDES 82
CURIUM BROMIDES 72, 119
CURIUM CHLORIDES 72, 165, 181
CURIUM COMPLEXES 76, 129, 134
CURIUM COMPOUNDS 66, 70, 74, 75, 79,
82, 83, 118, 157
CURIUM FLUORIDE 72, 80
CURIUM IONS 107
CURIUM ISOTOPES 23, 24, 69, 87, 88,
127, 168, 174
CURIUM NITRATES 143
CURIUM NITRIDES 74
CURIUM OXIDES 12, 13, 14, 15, 16, 17,
18, 19, 20, 30, 32, 73, 84, 116,
148, 151, 155, 164
CURIUM PHOSPHIDES 82
CURIUM SELENIDES 78
CURIUM SULFATES 143
CURIUM SULFIDES 78
CURIUM-240 107
CURIUM-241 95, 109
CURIUM-242 1, 12, 35, 48, 52, 55,
77, 97, 106, 116, 124, 143, 152,
154, 161, 163, 167, 172, 173
CURIUM-243 92, 93, 149, 157, 158
159, 173, 175, 176, 177
CURIUM-244 2, 3, 5, 7, 10, 12, 13,
14, 15, 16, 17, 18, 19, 20, 21, 22,
25, 26, 27, 28, 29, 31, 32, 33, 34,
36, 37, 38, 39, 40, 41, 42, 43, 44,
45, 46, 48, 49, 50, 51, 52, 55. 57,
59, 63, 65, 68, 77, 96, 100, 104,
110, 112, 115, 119, 120, 129, 140,
148, 149, 150, 151, 153, 155, 156,
157, 159, 160, 162, 164, 165, 166,
167, 170, 171, 173, 175, 177, 178,
182, 183, 184, 185
CURIUM-245 5, 11, 47, 103 105, 175,
176, 177
CURIUM-246 5, 94, 173, 177, 178, 185
CURIUM-247 10, 99, 177
CURIUM-248 5, 7, 21, 74, 80, 85, 94,
101, 114, 117, 123, 177
CURIUM-249 9, 80
CURIUM-250 86
CYCLOHEXANE 131
CYLINDRICAL CONFIGURATION 28
126
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DATA 138
DATA ACQUISITIONS SYSTEMS 8
D CODES 173
DCTA 75
DECAY 23, 169
DECONTAMINATION 77
DEFORMATION 8
DEFORMED NUCLEI 9
DEPOSITION 80, 156, 164
DEPTH DOSE DISTRIBUTIONS 154
DESIGN 8, 27, 29, 31, 33, 35, 37, 38,
40, 41, 42, 43, 44, 45, 46
DEUTERON REACTIONS 94, 107, 114, 117
DEUTERONS 85, 114, 174
DIAGRAMS 88
DIAMONDS 8
DIELECTRIC MATERIALS 8
DIELECTRIC PROPERTIES 70
DIFFERENTIAL CROSS SECTIONS 85
DIFFUSIONS 2, 3, 8, 12, 16, 17, 111
DISTANCE 89
DISTRIBUTION 123
DISTRIBUTION FUNCTIONS 133, 142
DOGS 148, 153, 156
DOPED MATERIALS 8
DOSE COMMITMENTS 170, 171, 173
DOSE RATES 151, 154
DOSE-RESPONSE RELATIONSHIPS 149, 150,
151, 152, 153
DRYING 48
DTPA 122, 161, 163, 170
DYSPROSIUM 81, 142
DYSPROSIUM IONS 113
DYSPROSIUM OXIDES 73
ECONOMICS 27, 33, 38, 42, 57
EDTA 124
EFFICIENCY 107
EIGEN FUNCTIONS 8
EINSTEINIUM 8, 81, 90, 91, 108
EINSTEINIUM COMPOUNDS 79
EINSTEINIUM-253 5, 6, 7, 21, 49,
149, 153, 162
ELECTRIC CURRENT 69
ELECTRIC POWER 168
ELECTRIC POTENTIAL 36, 69, 79, 145
ELECTRICAL PROPERTIES 73
ELECTROCHEMISTRY 108
ELECTRODEPOSITION 69, 98
ELECTRODES 69, 79
ELECTROLYSIS 69
ELECTROLYTES 73
ELECTRONS 81, 95
ELECTRON CAPTURE DECAY 95, 109
ELECTRONIC EQUIPMENT 39
ELECTRONIC STRUCTURE 4, 7, 71, 126
ELECTRON MICROSCOPY 8
ELECTRON SPIN RESONANCE 8
ELECTROPHORESIS 75, 124, 145
ELEMENTS 113
EMISSION 88
EMISSION SPECTRA 5, 6, 113
EMISSION SPECTROSCOPY 102
EMISSIVITY 20
ENERGY DEPENDENCE 174
ENERGY LEVELS 7, 9, 103, 114, 118
ENERGY LEVEL TRANSITIONS 7, 94,. 95,
117, 176
ENERGY SPECTRA 85, 96, 97, 110, 117,
177
ENTHALPY 71, 90
ENTROPY 68, 90, 91
ENVIRONMENT 2, 3, 24, 54, 167
ENVIRONMENTAL EFFECTS 1, 183
ENVIRONMENTAL STUDIES 2
EPIDERMIS 154
ERBIUM 81, 142
ERBIUM OXIDES 73
ESTERS 58, 139
ETHANOL 69
ETHYL ETHER 124
EUROPIUM 70, 81, 122, 124, 126, 128
129, 131, 132, 133, 134, 135, 141,
142, 144
EUROPIUM COMPLEXES 129, 134
EUROPIUM COMPOUNDS 8, 70, 75, 79
EUROPIUM IONS 113
EUROPIUM OXIDES 73, 84
EUROPIUM-152 129
EUROPIUM-153 103
EUROPIUM-155 140
EUTECTICS 8, 83, 130
EVAPORATION 6, 100
EVEN-ODD NUCLEI 9
EXCITATION 81, 123
EXCITATION FUNCTIONS 85
EXCRETION 155, 170, 171
FABRICATION 8, 12, 15, 16, 17, 18,
21, 30, 48, 49, 50, 84
FALLOUT 1, 124
FAULT TREE ANALYSIS 56
127
-------
FBR TYPE REACTORS 23
FCC LATTICE 74, 182
FECES 157, 170, 171
FERMIUM 89, 90, 91
FERMIUM COMPOUNDS 79
FERMIUM ISOTOPES 87
FERMIUM-255 7
FERMIUM-257 21, 49
FERMIUM-258 86
FERRITES 73
FERROELECTRIC MATERIALS 73
FISSILE MATERIALS 10
FISSION 11, 88, 123, 125, 174, 175
FISSION BARRIER 87
FISSION FRAGMENT DETECTION 105
FISSION FRAGMENTS 86, 87, 105, 120,
123
FISSION PRODUCTS 1, 11, 24, 62, 136
FISSION YIELD 11, 47, 86, 88, 123,
175
FLOWSHEETS 59
FLUIDIZED BED 56
FLUORESCENCE 101, 115
FLUORINE 6, 97
FOOD CHAINS 167
FORECASTING 24
FORMATION HEAT 79, 91, 181
FRANCIUM 108
FREEZING 48
FT VALUE 95
FUEL CYCLE 64, 168, 169
FUEL PELLETS 84
FUEL PROCESSING PLANTS 53
FUEL REPROCESSING PLANTS 61
FUSION HEAT 68
GADOLINIUM 8, 69, 70, 81, 142
GADOLINIUM COMPOUNDS 70, 79
GADOLINIUM OXIDES 73, 84
GADOLINIUM-153 183
GALACTIC EVOLUTION 99
GAMMA RADIATION 95, 109
GAMMA SPECTRA 95, 101, 109, 176
GAMMA SPECTROSCOPY 123
GAMMA TRANSITION 101
GASEOUS WASTES 53
GASTROINTESTINAL TRACT 162, 173
GEIGER-MUELLER COUNTERS 185
GEOLOGIC DEPOSITS 64
GERMAN FEDERAL REPUBLIC 53
GLASS 56
GLYCOPROTEINS 166
GOLD ALLOYS 8
GONADS 159
GRAPHITE 32
GROUND STATES 9
G VALUE 120
HAFNIUM 81, 141
HAFNIUM ALLOYS 8
HAFNIUM OXIDES 73
HALF-LIFE 22, 86, 95, 109, 116
HASTELLOY C 14, 15, 16, 18, 32
HAYNES ALLOYS 35
HAYNES 25 ALLOY 15, 16, 18, 32
HAYNES 188 ALLOY 32
HCP LATTICE 74
HDEHP 60, 131, 146
HEALTH AND SAFETY 2
HEALTH HAZARDS 2, 3, 168, 169
HEART 165
HEATING 106
HEAT RESISTING ALLOYS 8
HEAT TRANSFER 16
HELIUM 12, 15, 16, 17, 19
HELIUM IONS 106
HELIUM-3 REACTIONS 85, 174
HEMATOPOIETIC SYSTEM 149, 165
HEPTYL RADICALS 139
HIGH TEMPERATURE 83, 130
HOLLOW CATHODES 102
HOLMIUM 81, 113, 142
HOLMIUM COMPOUNDS 79
HOLMIUM OXIDES 73
HOT PRESSING 84
HTGR TYPE REACTORS 62
HUMAN POPULATIONS 2, 3, 169
HYDROCHLORIC ACID 131, 132, 133, 134,
135, 144, 181
HYDROGEN 120
HYDROGEN PEROXIDE 120
HYDROLYSIS 66, 67
HYDROXYL RADICALS 120
HYPERFINE STRUCTURE 180
IMPURITIES 52
INCONEL-600 14, 16
INDIUM 141
INELASTIC SCATTERING 94, 114, 117,
127
INFRARED SPECTRA 142
128
-------
INGESTION 153, 168, 169
INHALATION 148, 150, 151, 152, 153,
155, 156, 161, 164, 168, 169, 170,
171, 173
INJECTION 149, 152, 163
INTERACTION RANGE 89
INTERNAL CONVERSION 95, 101
INTERNAL IRRADIATION 149, 151, 152,
153, 170, 171, 173, 185
INTESTINAL ABSORPTION 162
INTRAMUSCULAR INJECTION 161
INTRATRACHEAL ADMINISTRATION 151
INTRAVENOUS INJECTION 157, 159, 165
IN VITRO 166
IODINE 6, 141
IODINE-129 24
IODINE-131 184
ION BEAMS 8, 69
ION EXCHANGE 59, 70, 124, 132, 136,
143, 144, 147
ION EXCHANGE CHROMATOGRAPHY 124, 132
IONIZATION CHAMBERS 105
IRIDIUM 30, 32
IRIDIUM ALLOYS 32
IRON 8
IRON COMPOUNDS 120
IRON-55 24
IRRADIATION 69
ISOMETRIC NUCLEI 184
ISOTOPE PRODUCTION 21, 23, 49, 51,
52, 55, 59, 80, 125, 136, 137
ISOTOPE RATIO 96, 124
ISOTOPES 169
keV RANGE 100-1000 157
KIDNEYS 160, 165, 173
KINETIC ENERGY 86
KRYPTON-85 53
LABORATORY ANIMALS 2, 152, 153
LABORATORY EQUIPMENT 8, 141
LANTHANUM 81, 124, 135, 141, 142
LANTHANUM COMPOUNDS 79
LANTHANUM OXIDES 73
LATTICE PARAMETERS 78, 82
LAVAGE 172
LAWRENCIUM 90, 91
LAYERS 69
LEACHING 56, 60, 63, 64
LEAD 135
LEAD-205 99
LET 120, 154
LIFETIME 36, 176
LIGANDS 129
LIQUID METALS 8, 68
LIQUID WASTES 51, 56, 59, 61, 63, 64
LITHIUM CHLORIDES 83
LITHIUM FLUORIDES 112
LITHIUM NITRATES 130, 142
LIVER 155, 157, 158, 160, 162, 163,
164, 165, 170, 173
LMFBR TYPE REACTORS 168, 169
LOW DOSE IRRADIATION 151
LOW TEMPERATURE 29
LUMINESCENCE 8
LUNG CLEARANCE 151, 164
LUNGS 148, 150, 151, 155, 156, 163,
164, 170, 172, 173, 183
LUTETIUM 81, 141, 142
LUTETIUM COMPOUNDS 79
LUTETIUM OXIDES 73
LYMPHOCYTES 172
MAGNESIUM OXIDES 8
MAGNETIC PROPERTIES 73, 179
MAGNETIC SUSCEPTIBILITY 182
MAMMALS 2
MAN 167, 168, 172, 173
MANGANESE-54 24
MARINE DISPOSAL 184
MASS 87, 88, 123
MASS NUMBER 86
MASS SPECTROSCOPY 136
MATERIALS 8
MATERIALS TESTING 17, 18
MAXIMUM ACCEPTABLE CONTAMINATION 154
M CODES 8
MEASURING METHODS 170, 171
MECHANICAL PROPERTIES 73
MEDIUM TEMPERATURE 75, 122
MELTING 56
MENDELEVIUM 90, 91
MERCURY 113
METALS 8, 73, 182
METHANE 105
METHANOL 144
METHODS 147
METHYL RADICALS 139
MeV RANGE 01-10 96, 154
MeV RANGE 10-100 85, 94, 114, 117,
127, 174
129
-------
MICROSPHERES 13, 14, 15, 16, 17, 18,
30, 151
MICROSTRUCTURE 8
MILKY WAY 99
MIXED SOLVENTS 143
MIXTURES 129
MOESSBAUER EFFECT 180
MOLECULAR BEAMS 68
MOLECULAR STRUCTURE 119
MOLTEN SALTS 83, 130, 142
MOLYBDENUM 13, 32, 141
MOLYBDENUM ALLOYS 32
MOLYBDENUM OXIDES 73
MOLYBDENUM-99 123
MONOCARBOXYLIC ACIDS 145
MONOCRYSTALS 8, 119
MORTARS 63
MUFFIN-TIN POTENTIAL 8
MULTIELEMENT ANALYSIS 136
MULTIPOLARITY 95, 127
MUSCLES 155
NEODYMIUM 81, 122, 124, 135, 142
NEODYMIUM IONS 113
NEODYMIUM OXIDES 73
NEODYMIUM-141 103
NEOPLASMS 151, 164, 173
NEPTUNIUM 4, 54, 55, 59, 60, 61, 62,
71, 81, 90, 91, 98, 124, 125, 130,
135, 137, 141, 142, 145, 146, 147,
179, 180
NEPTUNIUM COMPOUNDS 179
NEPTUNIUM ISOTOPES 88, 174
NEPTUNIUM-237 2, 10, 11, 55, 77, 100,
124, 162
NEPTUNIUM-239 124
NEUTRON BEAMS 8, 136, 175
NEUTRON DIFFRACTION 179
NEUTRON EMISSION 52
NEUTRON REACTIONS 11, 47, 52, 105,
177
NEUTRONS 107, 109
NEUTRON SOURCES 21, 49, 96, 97, 112
NEUTRON SPECTRA 96, 112
NEUTRON SPECTROMETERS 97
NICKEL BASE ALLOYS 8
NICKEL COMPOUNDS 8
NICKEL IONS 8
NICKEL-63 24
NILSSON-MOTTELSON MODEL 95, 176
NIOBIUM 141
NIOBIUM ALLOYS 8
NIOBIUM OXIDES 73
NIOBIUM SELENIDES 8
NIOBIUM-93 24
NITRATES 129, 162
NITRIC ACID 60, 65, 55, 128, 131,
133, 134, 135, 139, 140, 146
NOBELIUM 90, 91
NOBELIUM ISOTOPES 87
NTA 122
NUCLEAR EXPLOSIONS 1
NUCLEAR FUELS 23
NUCLEAR INDUSTRY 24
NUCLEAR POWER PLANTS 23, 24
NUCLEAR PROPERTIES 23
NUCLEAR REACTION KINETICS 174
NUCLEAR REACTIONS 88, 89
NUCLEAR REACTION YIELD 52
NUCLEAR STRUCTURE 103
NUCLEOSYNTHESIS 99
ODD-EVEN NUCLEI 9
OFF-GAS SYSTEM 53
ONE-NUCLEON TRANSFER REACTIONS 85
OPTICAL PROPERTIES 8
OPTIMIZATION 38
ORDER PARAMETERS 8
ORGANIC CHLORINE COMPOUNDS 77
ORGANIC ION EXCHANGERS 124, 143, 144
ORGANIC PHOSPHORUS COMPOUNDS 76, 133,
139
ORGANIC SOLVENTS 70
ORNL 64
OSCILLATOR STRENGTHS 118
OXIDATION 8, 14, 16, 30, 65, 71, 140
OXIDES 73, 84, 162
OXYGEN-18 52
OXYGEN COMPOUNDS 78, 140
OZONE 65
PAINTS 77
PAIRING INTERACTIONS 176
PALLADIUM-112 123
PALLADIUM HYDRIDES 8
PARITY 94, 117, 127
PARTICLE PRODUCTION 89
PARTICLES 168, 169
PARTICLE SIZE 132, 148, 155, 156
PARTITION 70, 130, 142
PATHOLOGICAL CHANGES 151, 153, 165
130
-------
PERCHLORIC ACID 67, 70, 131, 133, 134
PERFORMANCE 25, 31, 34, 45, 105
PERFORMANCE TESTING 13, 19, 35, 40,
185
PERMANGANATES 77
PEROXY RADICALS 120
PERSONNEL 2, 170, 171, 183, 185
PERSONNEL DOSIMETRY 170, 171, 185
PERSULFURIC ACIDS 139
PHASE TRANSFORMATIONS 8
pH FILTERS 147
PHOSPHINES 128
PHOSPHONIC ACID ESTERS 121, 134
PHOSPHORIC ACID 58, 65
PHOSPHOROUS OXIDES 131
PHROLYTIC CARBON 8
pH VALUE 145, 166
PHYSICAL PROPERTIES 8, 19, 125
PHYSICAL RADIATION EFFECTS 8, 106
PIEZOELECTRICITY 73
PILE NEUTRONS 11
PLANNING 43
PLATINUM 14, 106, 113
PLATINUM ALLOYS 32
PLUTONIUM 2, 4, 53, 54, 59, 60, 61,
62, 81, 89, 90, 91, 93, 98, 104,
111, 124, 125, 126, 130, 135, 136,
137, 141, 142, 143, 145, 146, 147,
172, 180
PLUTONIUM CARBIDES 8
PLUTONIUM CHLORIDES 119
PLUTONIUM COMPLEXES 163
PLUTONIUM COMPOUNDS 179
PLUTONIUM ISOTOPES 23, 87, 88, 168,
169, 174
PLUTONIUM NITRATES 143
PLUTONIUM OXIDES 13, 14, 15, 16, 17,
18, 30, 73, 107, 148, 151
PLUTONIUM-236 52, 100
PLUTONIUM-237 109, 158, 173
PLUTONIUM-238 2, 3, 10, 12, 13, 14,
15, 16, 17, 18, 24, 25, 26, 30.
31, 33, 38, 40, 41, 42, 43, 44,
45, 48, 52, 57, 97, 104, 107, 112,
115, 148, 151, 152, 153, 156,
161, 162, 167, 172, 173, 175,
184, 185
PLUTONIUM-239 2, 3, 10, 11, 12, 15,
24, 63, 92, 93, 100, 103, 109, 119,
124, 143, 148, 150, 151, 152, 153,
156, 159, 163, 166, 167, 172, 173,
183, 184, 185
PLUTONIUM-240 10, 22, 110, 114, 117,
124, 167, 173, 178, 185
PLUTONIUM-241 10, 11, 173, 175, 176
PLUTONIUM-242 173, 176, 178, 185
PLUTONIUM-243 173, 176
PLUTONIUM-244 99, 114, 117, 173
POINT DEFECTS 8
POLAROGRAPHY 79, 108
POLONIUM 135, 141
POLONIUM-210 26, 30, 39, 46, 48, 57,
153, 154
POLYETHYLENES 77
POLYMERIZATION 67
POLYPHENYLS 130, 142
POSITRONS 89
POTASSIUM CARBONATES 65
POTASSIUM CHLORIDES 83
POTASSIUM COMPOUNDS 139
POTASSIUM NITRATES 130, 142
POTENTIOMETRY 6
POWDERS 84
POWER 116
POWER CONDITIONING CIRCUITS 36
POWER RANGE 10-100 W 46
POWER REACTORS 51
POWER SUPPLIES 25, 26, 38, 40, 41,
42, 43, 44, 45
PRASEODYMIUM 65, 81, 124, 135, 142
PRASEODYMIUM OXIDES 73
PRECIPITATION HARDENING 8
PROBABILITY 88, 103, 117, 126, 127,
174
PRODUCTION 21, 49, 50
PROMETHIUM 55, 81, 122, 124, 133,
134, 135, 142
PROMETHIUM COMPLEXES 76, 134
PROMETHIUM OXIDES 73, 84
PROMETHIUM-147 55, 57, 124
PROMPT NEUTRONS 110, 175, 177, 178
PROTACTINIUM 62, 71, 81, 90, 91, 98,
141, 142, 145, 147, 180
PROTACTINIUM ISOTOPES 174
PROTACTINIUM-231 11, 100
PROTACTINIUM-233 100
PROTONS 107, 176
PROTON REACTIONS 107
PROTON RECOIL DETECTORS 96
PUREX PROCESS 61
PURIFICATION 18, 52, 100, 138
PVC 77
PYRAZOLES 60
PYRIDINIUM COMPOUNDS 135
131
-------
QUALITY FACTOR 154
QUANTITATIVE CHEMICAL ANALYSIS 124,
132, 172, 184
QUANTITY RATIO 69, 128
QUARTZ 8
QUASI PARTICLES 7, 9
QUATERNARY COMPOUNDS 135
R PROCESS 99
RADIATION ACCIDENTS 3
RADIATION DETECTION 183
RADIATION DOSE DISTRIBUTIONS 151,
155, 170, 171, 173
RADIATION DOSES 151, 152, 154, 168",
169, 170, 171, 173, 183, 185
RADIATION EFFECTS 8
RADIATION HAZARDS 3, 54, 62, 162,
173, 183
RADIATION MONITORING 1, 3, 53, 146,
184
RADIATION PROTECTION 2, 3, 53, 172,
183
RADIATION SOURCES 48, 116
RADIOACTIVE AEROSOLS 124, 148, 155
RADIOACTIVE EFFLUENT 184
RADIOACTIVE WASTE DISPOSAL 3, 56, 62,
64
RADIOACTIVE WASTE MANAGEMENT 3, 62
RADIOACTIVE WASTE PROCESSING 56, 59,
61, 62, 63, 64, 137
RADIOACTIVE WASTES 2, 20, 24, 53,
61, 64, 111, 167, 169
RADIOACTIVE WASTE STORAGE 54, 63
RADIOACTIVITY 3, 24, 69
RADIOBIOLOGICAL CONCENTRATION 167
RADIOBIOLOGY 2
RADIOCHEMICAL ANALYSIS 124
RADIOCHEMISTRY 125
RADIOINDUCTION 150, 151, 152, 164,
172
RADIOISOTOPE BATTERIES 13, 14, 15,
16, 17, 18, 28, 31, 32, 34, 36, 37,
40, 46, 57
RADIOISOTOPE HEAT SOURCES 12, 13, 14,
15, 16, 17, 18, 19, 20, 25, 26, 27,
28, 29, 30, 31, 32, 33, 34, 35, 37,
38, 39, 40, 41, 50, 57
RADIOLYSIS 120
RADIOMETRIC ANALYSIS 146, 170, 171,
184
RADIONUCLIDE ADMINISTRATION 152, 155
RADIONUCLIDE KINETICS 2, 146, 148,
149, 152, 155, 157, 158, 159, 160,
162, 164, 165, 170, 172, 173
RADIONUCLIDE MIGRATIONS 2, 111, 167,
184
RADIUM 60
RADON-222 150
RANGE 88, 107
RANKINE CYCLE 26, 29
RARE EARTH COMPOUNDS 84
RARE EARTHS 58, 60, 69, 71, 121, 139
RATS 150, 160, 161, 162, 163, 164,
165, 172
REACTOR FUELS 2
RECOILS 107
RECOVERY 20, 50, 57
REDOX POTENTIAL 71
REDUCTION 60, 83
REFRACTORIES 8
REMOVAL 77
RENAL CLEARANCE 157
REPROCESSING 50, 51, 54, 55, 58, 60,
61, 64, 137
RESEARCH PROGRAMS 6, 8, 12, 13, 14,
15, 16, 17, 18, 19, 20, 21, 26, 30,
35, 56, 172
RESINS 77, 132, 143
RESPIRATORY SYSTEM 151, 172
RESPONSE MODIFYING FACTORS 170
RETENTION 151, 155, 157, 158, 159,
162, 166
RETENTION FUNCTIONS 148, 170, 171
REVIEWS 141
RHENIUM 13, 30, 141
RHENIUM ALLOYS 18, 32
RHENIUM-187 99
RHODIUM 30
ROCKS 111
ROTATIONAL STATES 95
RUTHENIUM 56, 141
RUTHENIUM-106 184
SAFETY 54, 56
SAFETY STANDARDS 2
SALT DEPOSITS 64
SAMARIUM 69, 81, 122, 135, 142
SAMARIUM COMPOUNDS 79
SAMARIUM IONS 113
SAMARIUM OXIDES 73, 84
SAMARIUM-146 99
SAMARIUM-151 24
132
-------
SAMPLE PREPARATION 98, 184
SAMPLING 170, 171, 184
SATELLITES 25, 42, 43, 44, 45
SCALING 106
SCANDIUM 141
SCANDIUM OXIDES 73
SCATTERING 8
SEAS 39, 184
SEAWATER 1, 184
SEDIMENTS 184
SELENIUM-79 24
SELF-ABSORPTION 52
SENSITIVITY 102, 146
SEPARATION PROCESSES 51, 59, 60, 61,
64, 133, 137, 138, 139, 145
SHIELDING 18, 39
SILICON CARBIDES 8
SILVER NITRATES 139
SILVER-110 184
SILVER-111 123
SILVER-113 123
SINGLE INTAKE 149, 165
SINGLE-PARTICLE MODEL 7, 9
SINTERING 73
SKELETON 155, 157, 160, 162, 165, 170
SKIN 154
SKIN ABSORPTION 152, 153
SNAP BATTERIES 25
SNAP-7 BATTERY 14, 15, 16
SNAP-11 BATTERY 12, 13, 14, 35
SNAP-19 BATTERY 15
SNAP-21 BATTERY 14, 15, 16, 17
SNAP-23 BATTERY 15, 16, 17, 18
SODIUM CARBONATES 77
SODIUM COMPOUNDS 140
SODIUM FLUORIDES 77
SOILS 124
SOLAR CELLS 25
SOLIDS 73
SOLIDIFICATION 56, 63
SOLUTION HEAT 181
SOLVENT EXTRACTION 55, 58, 59, 60,
61, 124, 128, 129, 130, 131, 133,
134, 135, 139, 141, 142, 146
SOLVENT PROPERTIES 133, 135
SPACECRAFT POWER SUPPLIES 27, 30,
38, 40, 41, 46, 50, 57
SPACE FLIGHTS 25
SPACE VEHICLES 25, 26, 38, 40, 41
SPATIAL DISTRIBUTION 157
SPECIFIC HEAT 20. 179
SPECTRA 95, 183
SPENT FUELS 51, 54, 55, 58, 60, 61,
64, 137
SPIN 94, 117, 127
SPONTANEOUS FISSION 22, 86, 110, 123,
175, 177, 178
S PROCESS 99
STABILITY 54, 60, 69
STAINLESS STEELS 100
STAINLESS STEEL-304 15, 106
STAINLESS STEEL-316L 15, 16, 18
STANDARDS 2, 11
STARS 113
STATISTICS 183
STATISTICAL MODELS 174
STILBENE 97
STIRLING CYCLE 34
STRIPPING 85, 174, 176
STRONTIUM 55, 58, 141
STRONTIUM ALLOYS 18
STRONTIUM COMPOUNDS 13, 14, 15, 16,
17
STRONTIUM OXIDES 12, 14
STRONTIUM-85 63
STRONTIUM-89 123
STRONTIUM-90 13, 14, 15, 16, 17, 18,
53, 55, 183
STRONTIUM-91 123
STRUCTURAL CHEMICAL ANALYSIS 119
STRUTINSKY THEORY 7, 87
SUBLIMATION 80, 90
SUBLIMATION HEAT 91
SUDDEN APPROXIMATION 22
SULFATES 98
SULFONIC ACID ESTERS 70
SULFURIC ACID 120, 131
SURFACE CLEANING 77
SURFACE PROPERTIES 6
SYNERGISM 129, 142
TABLES 11
TANTALUM 13, 30, 32, 141
TANTALUM ALLOYS 32
TANTALUM ALLOY-T111 13, 17
TANTALUM-181 103
TARGETS 69, 80, 137
TBP 129, 130, 142
TDA 129
TECHNETIUM-99 24
TELLURIDES 179
TELLURIUM 141
TEMPERATURE DEPENDENCE 15, 32
133
-------
TERBIUM 81, 142
TERBIUM COMPOUNDS 79
TERBIUM OXIDES 73
TESTING 32
THALLIUM 135
THERAPY 163
THERMAL CONDUCTIVITY 12, 13, 14, 16,
17
THERMAL DIFFUSIVITY 30
THERMAL FISSION 11, 47, 177
THERMAL NEUTRONS 11, 47, 175
THERMIONIC CONVERTERS 46
THERMOCOUPLES 35
THERMODYNAMIC PROPERTIES 73, 90, 141
THERMOELECTRIC GENERATORS 25, 26, 27,
28, 31, 32, 33, 34, 35, 36, 37, 38,
39, 40, 41, 42, 43, 44, 45, 57
THICKNESS 107, 154
THIN LAYER CHROMATOGRAPHY 143
THIOCYANATES 144
THORIUM 4, 6, 62, 71, 81, 90, 91, 98,
104, 113, 130, 141, 142, 145, 146,
147, 180
THORIUM ISOTOPES 87, 88
THORIUM OXIDES 19, 32, 73
THORIUM-227 11
THORIUM-228 115, 166
THORIUM-229 11
THORIUM-230 114, 117, 127
THORIUM-232 11
THORIUM-234 100
THULIUM 70, 81, 141, 142
THULIUM COMPOUNDS 70
THULIUM OXIDES 73
THYROID 157
TIME DEPENDENCE 2, 149, 155, 157
TIN-121 123
TIN-125 123
TIN-126 24
TISSUE DISTRIBUTION 2, 148, 149, 152,
153, 155, 159, 165, 170, 172, 173
TISSUES 163
TITANIUM 69
TITANIUM ALLOYS 32
TOPO 129, 146
TOXICITY 164, 167, 168
TPO 129, 130, 142
TRACE AMOUNTS 121
TRACER TECHNIQUES 100, 158
TRANSMUTATION 64
TRANSPLUTONIUM ELEMENTS 9, 69, 80
TRANSURANIUM ELEMENTS 2, 3, 21, 49,
138, 153, 167, 168, 169
TRANS-104 ELEMENTS 7
TRITIUM 24, 53
TRITONS 85, 174
TTA 124, 142
TUNGSTEN 13, 17, 30, 141
TUNGSTEN ALLOYS 13, 18, 32
TUNGSTEN OXIDES 73
TURBOGENERATORS 29
ULTRASONIC TESTING 16, 17
ULTRAVIOLET SPECTRA 142
UNDERGROUND DISPOSAL 54
UNDERWATER 39
UNITED KINGDOM ORGANIZATIONS 172
UPTAKE 149, 151, 159, 166
URANIUM 4, 5, 23, 54, 59, 61, 62,
71, 81, 89, 90, 91, 98, 104, 124,
130, 135, 137, 141, 142, 145, 146,
180
URANIUM COMPLEXES 6
URANIUM COMPOUNDS 79, 179
URANIUM IODIDES 6
URANIUM ISOTOPES 87, 88, 127, 174
URANIUM ORES 60
URANIUM OXIDES 73
URANIUM-232 11, 100, 104, 115, 175
URANIUM-233 2, 10, 11, 47, 162, 183
URANIUM-234 22
URANIUM-235 5, 10, 11
URANIUM-239 176
URINE 146, 147, 157, 170, 171, 172
VALENCE 81, 139, 147
VANADIUM 106, 141
VANADIUM OXIDES 73
VAPOR PRESSURE 4, 16, 68
VARIATIONAL METHODS 89
VERY HIGH TEMPERATURE 32, 68, 84, 106
VIBRATIONAL STATES 94, 117, 127
VITRIFICATION 56
WATER 79, 139
WATER-COOLED REACTORS 62
WEIGHT 25
WELDED JOINTS 16, 17
WELDING 15
134
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WHOLE-BODY COUNTING 157, 158, 170,
171, 185
WHOLE-BODY IRRADIATION 173
WORKING FLUIDS 29
XENON-135 47
XENON COMPOUNDS 140
X-RADIATION 101, 104, 115, 126
X-RAY DIFFRACTION 78, 119
X-RAY SPECTRA 93, 101, 103, 104,
115
YTTERBIUM 69, 81, 142
YTTERBIUM COMPOUNDS 79
YTTERBIUM OXIDES 73
YTTRIUM 122, 124, 132, 133, 134, 141
YTTRIUM COMPLEXES 134
YTTRIUM OXIDES 73
YTTRIUM-90 124
ZINC COMPLEXES 163
ZIRCONIUM 141
ZIRCONIUM OXIDES 19, 73
ZIRCONIUM PHOSPHATES 138
ZIRCONIUM-93 24
ZIRCONIUM-95 184
135
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DISTRIBUTION
1-40 Environmental Monitoring and Support Laboratory-Las Vegas
41 Mahlon E. Gates, Manager, DOE/NV, Las Vegas, NV
42 Troy E. Wade, DOE/NV, Las Vegas, NV
43 David G. Jackson, DOE/NV, Las Vegas, NV
44 Paul J. Mudra, DOE/NV, Las Vegas, NV
45 El wood M. Douthett, DOE/NV, Las Vegas, NV
46 - 47 Ernest D. Campbell, DOE/NV, Las Vegas, NV
48 - 49 Paul B. Dunaway, DOE/NV, Las Vegas, NV
50 Roger Ray, DOE/NV, Las Vegas, NV
51 Robert W. Taft, DOE/NV, Las Vegas, NV
52 Leon Silverstrom, DOE/NV, Las Vegas, NV
53 Robert W. Newman, DOE/NV, Las Vegas, NV
54 Bruce W. Church, DOE/NV, Las Vegas, NV
55 - 56 Technical Library, DOE/NV, Las Vegas, NV
57 Chief, NOB/DNA, DOE/NV, Las Vegas, NV
58 Hal Hoi lister, GTN, DOE/HQ, Washington, DC
59 Tommy F. McCraw, DOS, DOE/HQ, Washington, DC
60 L. Joe Deal, DOS, DOE/HQ, Washington, DC
61 - 65 Major General Joseph K. Bratton, Director, MA, DOE/HQ, Washington,
DC
66 Gordon C. Facer, MA, DOE/HQ, Washington, DC
67 Robert L. Watters, OHER, DOE/HQ, Washington, DC
68 Jeff Swinebroad, OHER, DOE/HQ, Washington, DC
69 Robert W. Wood, OHER, DOE/HQ, Washington, DC
70 William S. Osburn, Jr., OHER, DOE/HQ, Washington, DC
71 Ray Brechbill, DOE/SAN, Oakland, CA
72 Marcy Williamson, RESL/INEL, DOE/ID, Idaho Falls, ID
73 Steven V. Kaye, Oak Ridge National Lab., Oak Ridge, TN
74 Helen Pfuderer, ESIC, Oak Ridge National Lab., Oak Ridge, TN
75 H. E. Walburg, CARL, Oak Ridge National Lab., Oak Ridge, TN
76 Assistant Administrator for Research and Development, EPA,
Washington, DC
77 Deputy Assistant Administrator for Monitoring and Technical Support,
ORD, EPA, Washington, DC
78 Acting Deputy Assistant Administrator for Radiation Programs, EPA,
Washington, DC
79 Director, Monitoring Technology Division, Office of Monitoring and
Technical Support, ORD, EPA, Washington, DC
80 Director, Technical Support Division, Office of Monitoring and
Technical Support, ORD, EPA, Washington, DC
81 Director, Criteria Development and Special Studies Division, Office
of Health and Ecological Effects, ORD, EPA, Washington, DC
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82 Library, EPA, Washington, DC
83 Regional Administrator, Region IX, EPA, San Francisco, CA
84 Regional Radiation Representative, Region IX, EPA, San Francisco, CA
85 Director, Radiochemistry and Nuclear Engineering Branch, EPA,
Cincinnati, OH
86 Director, Eastern Environmental Radiation Facility, EPA, Montgomery,
AL
87 Harold F. Mueller, NOAA/WSNSO, Las Vegas, NV
88 Gilbert J. Ferber, NOAA/WSNSO, Silver Spring, MD
89 K. M. Oswald, Manager, Health and Safety, LLL, Mercury, NV
90 Richard L. Wagner, LLL, Livermore, CA
91 Howard W. Tewes, LLL, Livermore, CA
92 Paul L. Phelps, LLL, Livermore, CA
93 Mortimer L. Mendelsohn, LLL, Livermore, CA
94 J. C. Hopkins, LASL, Los Alamos, NM
95 Harry S. Jordan, LASL, Los Alamos, NM
96 Lamar J. Johnson, LASL, Los Alamos, NM
97 George E. Tucker, Sandia Lab., Albuquerque, NM
98 Carter D. Broyles, Sandia Lab., Albuquerque, NM
99 Melvin L. Merritt, Sandia Lab., Albuquerque, NM
100 R. Glen Fuller, Oracle, AZ
101 Richard S. Davidson, Battelle Memorial Institute, Columbus, OH
102 Arden E. Bicker, REECo, Mercury, NV
103 Savino W. Cavender, REECo, Mercury, NV
104 Auda F. Morrow, CETO, Mercury, NV
105 Joseph H. Dryden, NTSSO, DOE/NV Mercury, NV
106 Billy Moore, NVHQ, DOE/NV, Las Vegas, NV
107 Leo Bustad, Director, Veterinary Medicine, Washington State
University, Pullman, WA
108 Vincent Schultz, Washington State University, Pullman, WA
109 Arthur Wallace, University of California, Los Angeles, CA
110 Wesley E. Niles, University of Nevada, Las Vegas, NV
111 Library, University of Nevada, Las Vegas, NV
112 Verle R. Bohman, University of Nevada, Reno, NV
113 Lloyd P. Smith, President, Desert Research Institute, University of
Nevada, Reno, NV
114 Paul R. Fenske, Desert Research Institute, University of Nevada,
Reno, NV
115 William S. Twenhofel, U.S. Geological Survey, Denver, CO
116 Manager, Desert National Wildlife Range, U.S. Fish and Wildlife
Service, Las Vegas, NV
117 Supervisor, Region III, Nevada Fish and Game Department, Las Vegas,
NV
118 Paul Lyons, Nevada Wildlife Research, Division of Archives, Capitol
Building Annex, Carson City, NV
119 Deward W. Efurd, McClellan Central Lab., McClellan Air Force Base,
CA
120 L. L. Skolil, San Diego State University, San Diego, CA
121 C. S. Fore, ESIC, Oak Ridge National Lab., Oak Ridge, TN
122 -148 Technical Information Center, DOE, Oak Ridge, TN (for public
availability)
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