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' Plutonium Battelle Memorial Institute / Pacific Noqthwest Laboratory 4,73' 1: ./ 9 J 4/ Lpcp I MASTE -64 . 11£747 ac Dfc BNWL-113 14 ..J ATTELLE= RTHWES I ' PLUTONIUM BATTELLE MEMORIAL INSTITUTE / PACIFIC NOQTHWEST LABORATORY ,- LAB8-11-IRAB-11"8 .11111 - pro,4.1,;,R;.;6...,I.,19,6;:52 VOLUME 6 NUMBER 2 March 31, 1966 PLUTONIUM ABSTRACTS IS A ·'CURRENT AWARENESS SERVICE'' TO THE ATOMIC ENERGY COMMISSION AND ITS RESEARCH AND DEVELOPMENT CONTRACTORS FOR NEW DEVELOPMENTS IN ALL AREAS OF PLUTONIUM TECHNOLOGY. MATERIAL IS COMPILED BY THE REFERENCE STAFF OF TECHNICAL INFORMATION. BATTELLE MEMORIAL INSTITUTE, PACIFIC NORTHWEST LABORATORY. THIS ISSUE COVERS THE FOLLOWING SUBJECT FIELDS: CFSTI PRICES Biology 8 Medicine , Chemistry 11,c. $.2. re ; »1 ..5-0 Health & Safety Metallurgy 4 Ceramics Miscellaneous Physics Reactor Technology RELEASED FOR ANNOUNCEMENT i-.IN NUCLEAR SCIENCE ABSTRACTS1 UC-2 GENERAL. MISCELLANEOUS AND PROGRESS REPORTS. TID-4500. PRINTED IN USA. PRICE $2.00 . AVAILABLE FROM THE CLEARINGHOUSE FOR FEDERAL SCIENTIFIC AND TECHNICAL INFORMATION. NATIONAL BUREAU OF STANDARDS. U. S. DEPARTMENT OF COMMERCE. SPRINGFIELD, VIRGINIA LEGAL NOTICE THIS REPORT WAS PREPARED AS AN ACCOUNT OF GOVERNMENT SPONSORED WORK. NEITHER THE UNITED STATES NOR THE COMMISSION. NOR ANY PERSON ACTING ON BEHALF OF THE COMMISSION: A. MAKES ANY WARRANTY OR REPRESENTATION. EXPRESSED OR IMPLIED. WITH RESPECT TO THE ACCURACY, COM- PLETENESS. OR USEFULNESS OF THE INFORMATION CONTAINED IN THIS REPORT. OR THAT THE USE OF ANY INFORMATION. APPARATUS. METHOD, OR PROCESS DISCLOSED IN THIS REPORT MAY INFRINGE PRIVATELY OWNED RIGHTS: OR B. ASSUMES ANY LIABILITIES WITH RESPECT TO THE USE OF. OR FOR DAMAGES RESULTING FROM THE USE OF ANY THIS REPORT. , INFORMATION. APPARATUS. METHOD. OR PROCESS DISCLOSED IN AS USED IN THE ABOVE. -PERSON ACTING ON BEHALF OF THE COMMISSION' INCLUDES ANY EMPLOYEE OR CON- TRACTOR OF THE COMMISSION. OR EMPLOYEE OF SUCH CONTRACTOR. TO THE EXTENT THAT SUCH EMPYOYEE OR CONTRAC- TOR OF THE COMMISSION. OR EMPLOYEE OF SUCH CONTRACTOR PREPARES. DISSEMINATES. OR PROVIDES ACCESS TO. ANY INFORMATION PURSUANT TO HIS EMPLOYMENT OR CONTRACT WITH THE COMMISSION. OR HIS EMPLOYMENT WITH SUCH CONTRACTOR. THE PACIFIC NORTHWEST LABORATORY IS OPERATED BY BATTELLE MEMORIAL INSTITUTE FOR THE UNITED STATES ATOMIC ENERGY COMMISSION UNDER CONTRACT AT (45.1)-1830. -· - - -- -C DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency Thereof, nor any of their employees, makes any warranty, express 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. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof. DISCLAIMER Portions of this document may be illegible in electronic image products. Images are produced from the best available original document. LEGAL NOTICE work. Neither the United an account of Government sponsored This report ..8 prepared as States, nor the Commission, nor any person actingexpressed on behalfor implied,of the Commission:with respect to the accu- < 4 or representation, A. Makes any warranty this report. or that the use or usefulness of the information contained in racy, completeness. process disclosed in this =i==...'..# method, or damagesreportresulting may not from infringe the "."'meduori h atus, respect to the use of, or for B. Awumes any liabilities with -2- or process disclosed in this report. any apparatus, method, Commission" includes any em- FOR ANNOUNCEMENT use of information, behalf of the -:4:FAI:, 1 31 the above, "person acting on - r :. - ·2. ; 1 . - ·.. < ployee Ao orusedcontractor in of the such contractor prepares. Commission.Commission, or employceor employee of such ofcontrar.tor, to the extent that such employee or contractor of the or contract 1 RELEASED any information pursuant to his employment „ IN NUCLEAR SCIENCE ABSTRACTS j dieseminates. or provides access to, such contractor. with the Commission. or his employment with Biology 6 Medicine 1748. ALPHA-ACTIVE FALLOUT PARTICLES; PHYSICAL CHARACTERISTICS RELATED TO PULMONARY EXPOSURE. Keith Jerome Schiager University of Michigan, Ann Arbor, Michigan. 1964. 132 p. Thesis. Nuclear Science Abstracts, Vol. 20: Abs. No. 1602. January 31, 1966. 1749. ANNUAL REPORT, UNIVERSITY OF ROCHESTER, ATOMIC ENERGY PROJECT. (University of Rochester, Rochester, N. Y.) UR-668. September 1, 1965. 166 p. Biological Effects of Inhaled Radioactive Materials (Inhalation Studies of Alpha Emitters), p. 58-60. The analytical work-up of the 1957 dog inhalation studies of plutonium1239 dioxide and in Vivo measurem*nts Of plutonium and uranium okides following inhalation exposures of dogs are summariked. Biological Effects of Inhaled Radioactive Materials. Dust Deposition and Retention. p. 108-109. In vivo measurements of pulmonary clearance were made on plutonium-238 dioxide and 10 other substances. 1750. DOSE DELIVERED TO THE THYROID GLAND AFTER INHALATION OF FISSION PRODUCTS. D. Mechali, M. Dousset, G. Pardoi M. Penotet (C.E.A., Paris, France) Health Physics, Vol. 12, No. 1: 15-27. January 1966. In French. Among the various hazards arising from the inhalation of fresh fission products, irradiation of the thyroid is important. This paper is concerned with 239 Pu fast neutron fission products and only bears on the case of a criticality accident when all the fissions occur within a very short lapse of time. The dose delivered to the thyroid by the several iodine isotopes after the inhalation of 1 mc of fission products has been calculated as a function of the time elapsed between plutonium fission and inhalation. The presence of the parents of the iodine isotopes in the mixture of fission products has been taken into account. 13 references. (auth.) I. 11 l -3- Biology 6 Medicine (Cont'd) 1751. PLUTONIUM URINALYSIS. N. Valentin, C. Wyers, R. Boulenger (Centre d'Etude de l'Energie Nucleaire, Brussels, Belgium) BLG-353. July 1965. 23 p. This report describes in detai.1 the.over-all procedure adopted for routine analysis at C.E.N., a modified form of the procedure developed at Los Alamos by Campbell and Moss. 1752. RESEARCH IN RADIOBIOLOGY. ANNUAL REPORT OF WORK IN PROGRESS . ON THE CHRONIC TOXICITY PROGRAM. Thomas F. Dougherty (University of Utah, Salt Lake City, Utah) COO-119-232. March 31, 1965. 222 p. Injection Tables, p. 5-62. Pu239 was one of five radio- nuclides injected in two groups of dogs - toxicity animals which will be maintained until sacrifice becomes a clinical necessity and test animals which may be sacrificed as needed for special studies. The injection history of each animal is given in tables, and comments made on the condition of the dead dogs. (B.G.R.) Pilot Study of the Effect of Cortisol on Na3CaDTPA En- hanced Excretion of Pu239 in the Beagle, p. 188-99. Two massive doses of cortisol were given to mobilize Pu239 to make it available for chelation by Na3CaDTPA and subsequent excretion. :No practically significant increase in excretion was observed, and there was no significant removal of Pu 2 ·39 from the dog's liver. (auth.) I -4- Chemistry 1753. BEHAVIOR OF Pu(V) IN NITRIC ACID SOLUTIONS. A. D. Gel'man, V. P. Zaitseva Soviet Radiochemistry, Vol. 7, No. 1: 58-68. January February,.1965. The behavior of Pu(V) in nitric acid solutions was in- vestigated within the interval pH = 2-6. It was shown that within the investigated pH region, the process of disproportionation influences the stability of Pu(V) solutions to a considerably lesser degree than the processes of oxidation and reductiob by radiolysis products. The basic causes of the instability of Pu(V) solutions of different concentrations within the interval pH = 2-6 were elucidated. The interval of pH values within which solutions of Pu(V) are the most stable was determined. 21 references. (auth.) 1754. CHEMICAL ENGINEERING DIVISION SEMIANNUAL REPORT. JULY-DECEMBER, 1964. (Argonne National .Lab., Argonne, Ill.) ANL-6925. May 1965. 263 p. The following sections of this report contain information about plutonium: pyrochemical process development - processes employing liquid metal solvents, p. 34-40, 48-49; pre- paration of fuels for fast reactors - homogeneous precipi- tation of UC and (U, Pu)C from fused salts, p. 101-103; fuel cycle applications of volatility and fluidization techniques, p. 107-110; laboratory investigations - fluid-bed fluorination of U308-PU02 mixtures, p. 110-116, fluorination of U02-PU02 pellets in a 2-inch diameter fluidized-bed reactor, p. 116-120, phase studies, p. 120- 122, reactions of PuF6, P· 122-123, alpha radiation decomposition rate of plutonium hexafluoride, p. 123-126; engineering-scale investigations of fluid-bed fluoride volatility processes - development of fluid-bed fluroide processes for the recovery of uranium and plutonium from uranium dioxide fuels, p. 132-139, 144-147; capture-to- fission ratios in EBR-II, p. 251; cost evaluation of metal- fueled fast reactors, p. 255-259; divisional study of reprocessing of fast reactor plutonium fuels, p. 259-263. 1 -5- Chemistry (Cont'd) 1755. CHEMICAL ENGINEERING DIVISION SEMIANNUAL REPORT. JANUARY- JUNE, 1965. (Argonne National Lab., Argonne, Ill.) ANL-7055. October 1965. 233 p. The following sections of this report contain information about plutonium: melt refining - extraction of plutonium from uranium-plutonium alloys with uranium trichloride, p. 21-26; processes employing liquid metal solvents - development of the blanket process,' p. 33, processes for fast breeder reactor fuels, p. 36-42, development of engineering equipment and procedures, p. 42-48; solid refractory fuels - preparation of (U-Pu)C solid solution, p. 90-94; fluorination of U02-Pu02 (and F.P.) pellets in a 2-inch diameter fluidized-bed reactor ' p.
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