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LAB8-11-IRAB-11"8 .11111 - pro,4.1,;,R;.;6...,I.,19,6;:52
VOLUME 6 NUMBER 2 March 31, 1966
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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. 105-114; reactions of bromine pentafluoride, p. 114-5; cleanup of cell exhaust air contaminated with plutonium hexa- fluoride, p. 145-47.
1756. CHEMISTRY OF NUCLEAR FUEL REPROCESSING. V. N. Prusakov, M. F. Pushlenkov Soviet Atomic Energy, Vol. 18, No. 2: 210-14. February 1965.
This is a review of reports in this field presented at the Third International Conference on the Peaceful Uses of Atomic Energy (Geneva, 1964). 37 references.
1757. COMPARISON OF SPECTROGRAPHIC METHODS OF ANALYSIS OF PLUTONIUM AND ITS COMPOUNDS. Michel Chaput, Jacques Robichet (C.E.N., Fontenay-aux-Roses, France) CEA-R-2869. September 1965. 36 p.
In French. The usual methods of spectrographic analysis are high voltage spark spectrography for plutonium in solution, and the method of carrier distillation for plutonium in the solid form. The sensitivities and the optimum conditions of the two methods are discussed. (E.R.A.)
1758. COMPLETE THERMODYNAMIC CHARACTERIZATION OF THE ELECTRODE PROCESSES WITH THE PARTICIPATION OF RARE EARTH AND ACTINIDE ELEMENTS. G. A. Krestove Soviet Radiochemistry, Vol. 7, No. 1: 69-77. January-February, 1965.
A complete thermodynamic characterization of a number of electrode processes with the participation of rare earth
(Cont'd) .
-6-
Chemistry (Cont'd)
1758. (Cont'd) and actinide elements is given on the basis of the intro- duction of the enthalpy and entropy components of the standard electrode potentials (41 And Il ). The electrode processes considered are classified with the aid of the numerical value and sign of the standard electrode potential and its components. Some peculiarities of these processes are noted. (auth.)
1759. COMPLEX FORMATION OF THE ACTINIDE ELEMENTS. I. Geletseanu, A. V. Lapitskii Soviet Radiochemistry, Vol. 7, No. 3: 279-81. May-June, 1965.
On the basis of the theoretical representations of the energies of the bonds accomplished by the 75-, 6d-, and: Sf-electrons, and the theory of the ligand field, a „ comparison of the stabilities of complex compounds of the actinide elements was made, using the material of a large number of experimental examples, taken from the literature data.
Considerations were expressed on the factors influencing the stability of the complex compounds formed by the actinide elements with different ligands. 33 references. (auth.)
1760. CONTINUOUS ELECTROWINNING OF PLUTONIUM METAL - SCALEUP STUDIES: PROGRESS REPORT. T. S. Soine (General Electric Co., Hanford Atomic Products Operation, Richland, Wash.) RL-SEP-244 DEL. April 1965. 39 p.
The conditions necessary for a cell capable of electro- winning plutonium metal from plutonium trichloride were established. The process is capable of handling PuC13 containing 10- 20% unchlorinated material (oxide). The electrowon product was substantially good. Cell life ·is the essential unsolved problem. Several methods for criticality hazards control are suggested. 12 references. -7-
Chemistry (Cont'd)
1761. CONTRIBUTION TO THE MICRO-CALORIMETRIC STUDY OF THE CHARACTERISTICS OF RADIO ELEMENTS AND TO THEIR QUALITATIVE AND QUANTITATIVE ANALYSIS. Yves Ozias (Universite d'Aix-Marseille, France) CEA-R-2630. (n.d.) 104 p.
In French. The principle of this study consists in using the E. Calvet microcalorimeter for recording the energy flux emitted by radio-elements as a function of time, and in determining from the curve either their characteristics (half-life and radiation energy), or the composition of a, mixture of radio-elements.
In the first part the theoretical relationships . describing radio-activity have been adapted to the micro- calorimetric study. In the second part an experimental determination has been made using the E. Calvet micro- calorimeter of the characteristics of various radio- elements, yttrium 90, phosphorus 32, sulphur 35, iodine 131, etc and of their mixtures. In particular a study has been made of the isotopic analysis of a 239 PU_240 PU mixture, sometimes in the presence of 241PU.
The microcalorimctric method i3.not 83 3ensitive as conventional counting methods, its limit appears to be at the present about 1 microwatt for the apparatus used, it is however the most direct method in the case of emitters of weakly absorbed radiation (a and B). For the y emitters only a part of the energy is absorbed by the walls of the container. The determination of their characteristics and of their masses in the mixtures depends neither on the shapei on the dilution or even less on the auto-absorptioh of the source. For high- activity samples this auto-absorption is the cause of great difficulties in conventional methods which complicate the operations: divisions, dissolutions, dilutions, all of which are liable to introduce errors. The calorimetric method makes it possible to work on the untreated sample. All these measurements have been carried out using the conventional E. Calvet calorimeter; to carry out an exact measurement of the energy due to y radiation, how- ever, it is necessary to build special apparatus with a lead block the size of which is given by the author's calculations.
The calorimetric method makes it possible to attain an accuracy equal to that obtained by mass spectrography (destruction of the sample) 1 to 3 per cent, and higher than that obtained by counting techniques (greater than 5 per cent). 18 references. (auth.)
/1 -8-
Chemistry (Cont'd)
1762. CORRELATION BETWEEN THE EXTRACTING POWER OF.ORGANOPHOSPHORUS EXTRACTING AGENTS AND THE [HAMMETT] a CONSTANT OF THE SUB- STITUENTS ON THE PHOSPHORUS ATOM. A. V. Nikolaev, I. N. Gribanova, N. I. Yakovleva, V. B. Durasov, I. D. Khol'kina, Z. N. Mironova, E. N. Tsvetkov, M. I. Kabachnik Doklady Akademii Nauk SSSR, Vol. 165, No. 3: 578-81. 1965.
In Russian. Chemical Abstracts, Vol. 64, Abstract No. 5824e. February 28, 1966.
1763. CRITICAL TEMPERATURE OF PLUTONIUM-CHLORINATED SOLVENT REACTIONS. S. H. Pitts, Jr. (The Dow Chemical Co., Recky Flats Division, Golden, Colo.) RFP-688. February 18, 1966. 9 P.
Critical temperatures were determined for some plutonium- chlorinated solvent reactions. These temperatures were determined by heating plutonium samples to a known temperature in argon and dropping them into various solvents while visually watching for a reaction.
A correlation was established between the critical temperature and surface area for unalloyed and 1 w/0 gallium alloyed plutonium in several chlorinated solvents. The critical temperature decreases as the specific surface area is increased.
1,1,1-trichlorethane, trichloroethylene, perchloroethylene, and 1,1,2-trichloro-1,2,2-trifluoroethine react with plutonium, but the reaction is milder and seldom goes to completion as it does in CC14· CC14 consistently had the lowest critidal temperatures. Chlorothene and Freon TB-1 solvents had essentially the same critical temperature which was lower than for perchloroethylene and 1,1,2- trichloroethylene. Of the solvents studied, trichloro- ethylene was the least reactive and therefore the safest under these test conditions.
In general, unalloyed plutonium exhibited a lower critical tebperature than gallium stabilized delta phase plutonium.
The critical temperature of plutonium in CC14 was increased by the addition of Texaco Regal cutting oil. The addition of plutonium oxide, plutonium chloride, water, or chlorine to Ccl.4 did not lower tho critical temperature of plutonium. Both acetone and methanol added to CC14 suppressed the reaction and increased the critical temperature. (auth.) -9-
Chemistry (Cong,d)
1764. THE DETERMINATION OF LOW LEVEL PLUTONIUM ACTIVITY; AUTORADIO- GRAPHIC TECHNIQUES VS. SCINTILLATION.COUNTING. William D. Moss, Evan E. Campbell (Los Alamos Scientific Lab., Los Alamos, N. Mex.) LA-DC-7483. 1965. 7 P.
The two techniques were found to be equilly accurate and dependable, but the Los Alamos Lab. is returning to scintillation counting for routine plutonium plates because the analysis is faster, there is smaller opportunity for human error, and a microscopist is released for other tasks.
1765. ENTROPY CHARACTERISTICS OF THE SHORT-RANGE AND LONG-RANGE HYDRATION OF IONS OF THE RARE EARTH AND ACTINIDE ELEMENTS. G. A. Krestov Soviet Radiochemistry, Vol. 7, No. 3: 304-308. May-June, 1965.
The entropy characteristics of the short- and long-range hydration of monoatomic ions of the rare earth and actinide elements were determined. The peculiarities of the variation of the entropy of water in the region of Lhe bhort- and long-range hydration and their dependence on the basic characteristics of the ion (charge and radius) were noted, and the interrelationship of these quantities with the coordination numbers were discussed. 13 references. (auth.)
1766. EUROCHEMIC SECOND ACTIVITY REPORT; 1962-1964. (European Nuclear Energy Agency, Paris, France) NP-15406. (n.d.) 313 p.
Promising results were obtained in the.use of uranium (IV) nitrate solution as the reducing agent for plutonium (IV) in the partition cycle. p. 92.
The process for the final purification of plutonium has been studied. The results on the use of trilaurylamine as an extractant enabled the work on ion exchange to be stopped, and a particularly promising method for pre- cipitating the plutonium from the organic phase has been developed. In parallel with the work on TLA, quaternary ammonium compounds were also investigated as extractants, and some tests were also made of the conditioning of the plutonium product obtained by precipitation. p. 111-123. Plutonium laboratory determinations are discussed on p. 125. (auth.) -10-
Chemistry (Cont'd)
1767. EVALUATION OF THE METHODS IN TID-7029, "SELECTED MEASUREMENT METHODS FOR PLUTONIUM AND URANIUM IN THE NUCLEAR FUEL CYCLE." M. W. Lerner (U.S.A.E.C., New Brunswick Lab., New Brunswick, N. J.) NBL-231. February 15, 1966. 127 p.
The purpose of this study was to evaluate, from the experience of several laboratories, the methods given in TID-7029, which for the most part contained methods of analysis tried out in only one laboratory. Nine methods for measurement of plutonium concentration, one method for measurement of plutonium isotopic concentration, one method for determination of iron in plutonium and plutonium compound solutions, and a method for anion- exchange separation of plutonium from diverse ions are given.
1768. EXTRACTION OF COMPLEXES OF ELEMENTS WITH 1-PHENYL-3-METHYL-4- BENZOYL-5-PYRAZOLONE. Yu. A. Zolotov, V. G. Lambrev, M. K. Chmutova, N. T. Sizonenko Doklady Akademii Nauk SSSR, Vol. 165, No. 1: 117-20. 1965.
In Russian. Chemical Abstracts, Vol. 64: Abs. No. 280ld. January 31, 1966.
1769. FINAL PURIFICATION OF PLUTONIUM AND CONDITIONING OF THE PRODUCT. H. B. Ludwig, E. Lopez-Menchero, J. van Geel (Eurochemic Co., Mol, Belgium) Atomptaxis, Vol. 12, No. 1: 36-41. January 1966.
The plutonium tail-end unit of the Eurochemic plant, serving for both a tributylphosphate solvent extraction process and a trilaurylamine solvent extraction process is described. The design principles of the equipment and its lay-out are given. (auth.)
1770. INFLUENCE OF SALTING-OUT AGENTS ON- THE ACTIVITY COEFFICIENTS OF URANIUM AND PLUTONIUM IN NITRIC ACID SOLUTIONS. 0. N. Shuvalov Soviet Radiochemistry, Vol. 7, No. 3: 263-268. May-June, 1965.
The influence of Al(N03)3, Mg(N03)3, and NH4N03 on the i activity coefficients of U(VI), pu(VI), and Pu(IV) was investigated in solutions of uranium and nitric acid. The Harned coefficients were determined for U(VD and Pu(VI). It was shown that the activity coefficients of Pu(IV) and the extraction constants of HN03 in the presence of salting-out agents fit on smooth curves. 15 references. (auth.) -11-
Chemistry (Cont'd)
1771. IMPROVED EXTRACTION METHOD FOR ISOLATION OF TRIVALENT ACTINIDE - LANTHANIDE ELEMENTS FROM NITRATE SOLUTIONS. F. L. Moore (Oak Ridge National Lab., Oak Ridge, Tenn.) Analytical Chemistry, Vol. 38, No. 3: 510-12. March 1966.
The method described is based on the liquid-liquid extraction of trivalent actinide-lanthanide elements from relatively dilute solutions of aluminum nitrate- nitric acid with a quaternary ammonium salt, tricapryl- methylammonium nitrate. Recovery of these elements from plutonium process waste solutions is good.
1772. THE IMPURITY ANALYSIS OF PLUTONIUM PEROXIDE AND PLUTONIUM FLUORIDE. A. J. Johnson, E. Vejvoda (The Dow Chemical Co., Rocky Flats Division, Golden, Colo.) RFP-599. February 4, 1966. 7 P.
A review. has been made of.the spectrographic methods used for the impurity analysis of plutonium peroxide and plutonium fluoride. For comparison purposes, the impurity analyses on nitrate feeds, peroxides, fluorides, and metal buttons are reported. (autll.)
1773. ISOTOPES AND RADIATION. A. S. Shtan' Soviet Atomic Energy, Vol. 18, No. 3: 327-31. March 1965.
This is a review of papers in the field of isotope production and utilization presented at the Third International Conference on the Peaceful Uses of Atomic Energy. The production of Pu-238, the production of Cm-244 from Pu-239, characteristics of SNAP generators fueled with Pu-238, and production of Cm242 as an end result of B decay of Pu-241 are briefly described.
1774. MEASUREMENT OF RADIOACTIVITY AT THE SURFACE OF AQUEOUS SOLUTIONS. M. A. Belokurova, N. E. Tsvetaeva, M. N. Kulichenko, L. A. Ivanova Soviet Atomic Energy, Vol. 18, No. 3: 380-82. March 1965.
Pu-239 activity was measured at the surface of alkaline, weakly acid and acid solutions. (0.5 and 1.0 N HN03)· Considerable discrepancy was observed between parallel samples, increasing with time. This is attributed to sorption at the air-water interface. -12-
Chemistry (Cont'd)
1775. MOUND LABORATORY PROGRESS REPORT FOR MAY, 1965. J. F. Eichelberger, G. R. Grove, L. V. Jones (Monsanto Research Corp., Mound Lab., Miamisburg, Ohio) MLM-1266. October 29, 1965. 36 p.
Preparation of Sources for Alpha Spectrometry. p. 11-18. A simple method was developed for the preparation of alpha sources to be analyzed by an alpha spectrometer equipped with a semi-conductor detector. The procedure consists of evaporating to dryness an aqueous solution of the alpha-emitter, redissolving the residue in situ with 0.1 N HN03, precipitating with 3 N NH4OH and drying. The residual NH4N03 is redissolved in 3 N NH4OH, dtied again, and sublimed at a higher temperature. The deposit is washed with distilled water, after which the plate is dried and ignited at red heat. Dramatic improvement is illustrated with several alpha emitters of different chemical properties, including polonium-208 and -209, thorium-230, protactinium-231, uranium-232 and -234, and plutonium-238 and -239.
By providing better distribution of the alpha-emitting nuclides and by removing alpha-absorbing impuritics, the same procedure significantly increases the gross alpha couting rate and is recommended for use in improving the accuracy and reproducibility of routine alpha counting. 10 references. (auth.)
1776. THE NATURE OF WATER BONDS IN CRYSTALLINE HYDRATES OF URANIUM I AND PLUTONIUM TETRAFLUORIDES. E. G. Tetetin, E. I. Khanaev (Inst. Inorg. Chem., Novosibirsk) Izvestiya Sibirskogo Otdeleniya Akademii Nauk SSSR, Seriya I Khimicheskikh Nauk, 1965, No:. 2: 51-62.
In Russian. Chemical Abstracts, Vol. 64: Abs. No. 437Ob. February 14, 1966.
1777. PARTIAL THERMODYNAMIC EQUILIBRIA IN NONEQUILIBRIUM SYSTEMS. I. INTERACTION OF PLUTONIUM WITH HYDROGEN PEROXIDE IN THE PRESENCE OF VARIOUS LIGANDS. B. P. Nikol'skii, M. V. Posvol'skii, L. I. Krylov Soviet Radiochemistry, Vol. 7, No. 3: 297-303. May-June, 1965.
The interaction of plutonium with hydrogen peroxide under conditions of complex formation leads to the establishment of thermodynamic equilibrium among the valence forms of
(Cont'd) -13-
Chemistry (Cont'd)
1777. (Cont'd) and electrons, the activity of 'which'is set in such solutions by the ratio 6f the kinetic factors of the oxidation and reduction of'h9drogan peroxide. The ratio of the valence forms at equi,librium depends primarily on the nature of the addend, as well as on the total plutonium concentration in solution. As the total plutonium concentration in solution increases, the content of "oxidized" forms drops.
Equilibrium in buffered solutions of malonic and maleic acids is shifted toward· the formation of oxidized forms; in solutions of complexones it is shifted toward reduced forms: This is related to the relative strength of the complexes formed by different valence forms of plutonium with the peroxo-group, on the one hand, and with different organic ligands, on the other. The oxidized form in malonate buffer shlutions is pentavalent plutonium. Hexavalent plutonium is practically absent. The reduced form is tetravalent plutonium. The interaction of any valence form of plutonium with H202 in a malonate buffer solution at a total plutonium concentration of the order of 10-4 M and less may be used as a preparative method for the production of Pu(V). (auth.)
1778. PLUTONIUM RELEASE STUDIES. I. RELEASE FROM THE IGNITED METAL. J. Mishima (Battelle Memorial Institutei Pacific Northwest Lab., Richland, Wash.) BNWL-205. December 13, 1965. 24 p. Six plutonium rods, 1/4-inch in diameter and 3/4-inch in length, were ignited in dry air at temperatures ranging from 410 to 650'C. Air·drawn over the specimens at velocities ranging'from 3.'3 to 50 cm/sec was examined for particulate plutoniwn oxide. Plutonium oxide entrained ranged from 3 x 10-6 to 5 x 10-5 w/o. The entire oxide produced was subsequently sized using an elutriation- sieving technique. The quantity of particulate material less than 15 microns was found to depend upon the mechanical work used in sizing the particles. ·Particles equivalent to less than 15 microns in diameter represented as much as 0.03 w/0 of the total oxide and 70 -'·80 per cent of this material was less than 0.1 micron ·in size. Oxidation conditions producing. internal· stresses in the oxide increase friability. Less friable oxides are produced by high oxidation ·temperatures. Increasing particle size is found with increasing oxidation temperatures. The amount and rate of release under any· stated conditions is dependent on friability and the forces to which the oxide mass is subjected. Results of this study are compared with other data available relating to particle size and fractional release from ignited plutonium. Reasonable agreement is noted. (auth.) -14-
Chemistry (Cont'd)
1779.. PRODUCTION AND CERTAIN PROPERTIES OF NITRIC ACID SOLUTIONS OF PU(V). A. D. Gel'man, V. P. Zaitseva Soviet Radiochemistry, Vol. 7, No. 1: 48-57. January-February, 1965.
The conditions of production of nitric acid solutions of Pu(V), with a concentration of 2 x 10-2 M, by the reduction of hexavalent plutonium with hydrogen peroxide were determined. A calibration curve was given for the ab- sorption density of nitric acid solutions of Pu(V) as a function of the pentavalent plutonium concentration in solution. A spectrophotometric investigation was made of nitric acid solutions of Pu(V) within the interval of pH = 2-6. It was established that within this pH interval, nitric acid solutions of Pu(V) possess analogous A spectra, which is evidence of the absence of processes ' of complex formation and hydrolysis. Up to pH = 3, nitric acid solutions of Pu(V) with a concentration greater than i 1,10-2 M contain Pu(VI) in solution. At an initial PH > 3, a lowering of the Pu(VI) concentration in solution is observed and only after a month does Pu(VI) appear. 17 references. (auth.)
1780. THE PRODUCTION OF Pu-242 AND Cm-242 BY IRRADIATING Am-241 WITH NEUTRONS. V. B. Dedov, V. V. Volkov, B. A. Gvozdev, V. A. Ermakov, I. A. Lebedev, V. M. Razbitnoi, P. S. Trukhlyaev, Yu. T. Chuburkov, G. N. Yakovlev ORNL-TR-892. (n.d.) 21 p.
This is a translation of Radiokhimiya, Vol. 6, No. 4: 453-61. 1965.
The results of the chemical separation of Pu-242, Cm-242 and Am-243 from irradiated Am-241 are presented. Solvent extraction and chromatographic methods were used primarily.
1781. THE RAPID DISSOLUTION OF PLUTONIUM DIOXIDE BY A SODIUM PEROXIDE SINTER, FOLLOWED BY DETERMINATION OF THE PLUTONIUM CONTENT BY DIFFERENTIAL SPECTROPHOTOMETRY. G. W. C. Milner, D. Crossley, I. G. Jones, G. Phillips (Atomic Energy Research Establishment, Harwell, U.K.) The Analyst, Vol. 90, No. 1077: 732-35. December 1965.
A method is described for the dissolution of plutonium dioxide and the determination of the plutonium content
(Cont'd) -15-
Chemistry (Cont'd)
1781. (Cont'd) by differential spectrophotometry. The plutonium dioxide is brought into solution by mixing with excess of sodium peroxide and heating at. 400'C for 10 minutes, followed by the addition of a similar amount of sodium hydroxide and re-heating for a further 10 minutes. The cold sinter is then extracted with water and transferred to hydrochloric acid solution containing hydroxylammonium chloride. The solution is heated to decompose the peroxide and reduce the plutonium to the tervalent state. The plutonium concentration is then determined by differential spectro- photometry in 4-cm bells at 565 mu, comparing with standards prepared from plutonium metal. Mean recoveries on 100-mg amounts .of plutonium dioxide.that had been ignited at 850'C were 99.8 per cent with a coefficient of variation of 0.3 per cent. Similar results were obtained on plutonium dioxide that had been ignited to 1550'C, by slightly extending thE sintering time. (auth.)
1782. SOLUBILITY PRODUCT OF AMMONIUM PLUTONYL PHOSPHATE IN AQUEOUS SOLUTIONS. R. G. Denotkina, V. B. Shevchenko, A. I. Moskvin Zhurnal Neorganicheskoi Khimit Vol. 10, No. 11: 2449-52. 1965.
In Russian. Chemical Abstracts, Vol. 64: Abs. No. 2805c. January 31, 1966.
1783. STATE OF Pu(IV) IN THE REGION OF PH = 1.0 -· 12.0 AT A PLUTONIUM CONCENTRATION OF 2 X 10-5 M. V. I. Grebenshchikova, Yu. P. Davydov Soviet Radiochemistry, Vol. 7, No. 2: 190-93. March-April, 1965.
It was shown by comparing the results of experiments on the adsorption and desorption of plutonium(IV) from silica gel, ultrafiltratiOn, and centrifugation, that at a concentration of 2.10-5 M quadrivalent plutonium exists in solution in ionic form up to pH = 1.4, while beginning with pH = 1.5 and up to the pH = 12.0 studied, it exists in the colloidal state with various degrees of dispersion of the collidal particles. It was shown that the re- charging of colloidal particles of plutonium(IV) is observed at pH = 8.0-8.5. 15 references. (auth.) -16-
Chemistry (Cont'd)
1784. STUDY OF THE ADSORPTION OF TRANSURANIZIM ELEMENTS BY CHROMATO- GRAPHY ON ION-EXCHANGE PAPERS. I. PLUTONIUM (IV) AND PLUTONIUM (VI) IN NITRIC MEDIUM. Monique Pagos, Frank Clanet (Curie Lab., Radium Institute, Paris, France) Journal of Chromatography, Vol. 21, No. 1: 105-12. January 1966.
In French. The adsorption of Pu(IV) and Pu(VI) on paper impregnated with ion-exchange resins has been studied in nitric acid, concentration range 0.5-15 M. Evidence has been ut forward for the existence of the species Pu(N03) 3 and Pu022+ in 1-4 M HN03• 'Some partition coefficients are given. (auth.)
1785. THREE-WAVELENGTH X-RAY ABSORPTION EDGE METHOD FOR DETERMINATION OF PLUTONIUM IN NITRATE MEDIA. E. A. Hakkila, R. G. Hurley, G. R. Waterbury (Los Alamos Scientific Lab., Los Alamos, N. Mex.) Analytical Chemistry, Vol. 38, No. 3: 425-27. March 1966.
A new x-ray absorption edge method was developed for determining plutonium in nitrate solutions. In this method the transmitted x-ray intensities at three wavelengths are measured. The KB x-ray for niobium and the Ka x-rays for molybdenum and niobium are produced by irradiating a niobium-molybdenum secondary target with x-rays from a tungsten-target x-ray tube, and the intensities of these x-rays are measured after passing through an absorption cell filled successively with water and a solution of known plutonium content. Then the reduction in the transmitted intensities of the KB x-ray for niobium and the Ka x-ray for molybdenum, which bracket the L III absorption edge for plutonium, are measured through the same cell filled with the sample solution. The absorption of these x-rays is related to plutonium concentration using accepted absorption principles. The method is applicable to the determination of plutonium concentrations of 10 to 25 mg. per ml. with a relative standard deviation of approximately 0. 6%. (autli.) -17-
Health 6 Safety
1786. APPARATUS FOR MONITORING 239 Pu IN WOUNDS. R. J. Epsteini E. W. Johanson (Argonne National Lab., Argonne, Ill.) Health Physics, Vol. 12, No. 1: 29-35. January 1966.
An instrument has been designed for the detection of 239 PU in wounds. The detector is a NaI(Tl) scintillation counter, optimized for the detection of soft X-rays. With this apparatus it is possible to detect 5 x 10-4Wc of 239 Pu, as a distributed source, at the surface of a wound, with a source count rate equal to that for the background. Re- solution for 14.4 keV gammas is about 30 per cent. At 6.4 keV the peak to low-energy-valley ratio is about 9 to 1. The detector is supported by a mechanism which is convenient for clinical use. An attendant optical system projects crossed light beams along the counter axis for convenient determination of the source location. Data is presented as a spectrum on a multichannel analyzer and as a display of the total number of counts in the energy region of interest. A discussion of error minimizing procedures is presented. 14 references. (auth.)
1787. DECONTAMINATION PROCEDURES AND FREQUENCIES IN a-B -y METALLURGICAL HOT CELLS. A. Valentin, L. Hayet (C.E.N., Fontenay-aux-Roses, France) International Symposium on· Working Methods ih High Actiyity Hot Laboratories. Vol. II. Paris, Organization for Economic Cooperation and Development, 1965. p. 735-47.
In French. Nuclear Science Abstracts, Vol. 20, Abs. No. 4213. February· 15, 1966.
1788. FAST REACTOR SAFETY CONSIDERATIONS RELATED TO FUEL MACRO-STRUCTURE. R. E. Peterson, S. Goldsmith (Battelle Memorial Institute, Pacific Northwest Lab., Richland, Wash.) BNWL-SA-346. October 6, 1965. 19 P.
Thermal properties of Pu02, PuC, PuN, PuS, and SS-20 v/0 PU02 are included in this report. It is concluded that thermal and elastic properties related to fuel macro- structure can be of the utmost importance in fast reactor power excursions in the prompt critical range. -18-
Health 6 Safety (Cont'd)
1789. HAZARDS CONTROL QUARTERLY REPORT NO. 21. (APRIL-JUNE, 1965). (University of California, Lawrence Radiation Lab., Livermore, Calif.) UCRL-14351. (n.d.) 37 p.
Transistorized Solid-State Plutonium-Alpha Air Monitor, p. 10-15.
A more compact, solid-state plutonium air monitor has been designed, using transistorized circuitry, and is less expensive than the current model. (auth.)
1790. SAFETY PRECAUTIONS TO PREVENT CRITICALITY ACCIDENTS. W. Schiiller, H. Ziind (Eurochemic Co., Mol, Belgium) Atompraxis, Vol. 12, No. 1: 47-50. January 1966.
In German. , The application of criticality control methods is briefly discussed and illustrated by describing how nuclear safety requirements are fulfilled in the different processing stages of the Eurochemic irradiated fuel reprocessing plant. Inherently safe equipment is not always compatible with process or economic requirements and some reliance must often be placed on safe operating procedures. It is emphasized that the necessary controls must be enforced by exhaustive operation manuals and adequate training of plant personnel. (auth.)
1791. WORKING METHODS - EQUIPMENT IN USE AT THE 1000 CURIE - 1 Mev TRANSPLUTONIUM COMPLEX AT THE MEDIUM ACTIVITY LABORATORY. J. M. Gandolfo (C.E.N., Mol, Belgium) International Symposium on Working Methods in High Activity Hot Laboratories. Vol. II. Paris, Organization for Economic Cooperation and Development, 1965. p. 791-804.
In French. Nuclear Science Abstracts, Vol. 20, Abs. No. 4065. February 15, 1966. 119 -
Metallurgy and Ceramics
1792. BEHAVIOR OF SOME DELTA-STABILIZED -PLUTONIUM-GALLIUM ALLOYS AT HIGH PRESSURES. R. 0. Elliott, K. A. Gschneidner, Jr. (Los Alamos Scientific Lab., Los Alamos, N. Mex.) LA-2312. April 1, 1959. 20 p.
A number of delta-stabilized plutonium-gallium alloys were subjected to ptessures as high as 11,000 atm at 24'C. Trandformation pressures and .volume's, compressibilities, densities, and hardnesses of these- alloys were determined as a function of composition, and the effect of gallium content on the stability of delta plutonium was studied and related to the plutonium-gallium phase diagram. (auth.)
1793. GROWTH OF SINGLE CRYSTALS OF PLUTONIUM. PROGRESS REPORT OCTOBER 1, 1965 TO DECEMBER 31, 1965. (Nuclear Materials and Equipment Corp., Apollo, Pa.) NUMEC-3428-17. February 1, 1966. 8 P.
A number of high pressure runs were made on high purity alpha plutonium at various time and: temperature cycles, but single crystal alpha plutonium was not attained. *
1794. KINETICS OF THE a *B TRANSFORMATION OF PLUTONIUM IN THE VICINITY OF EQUILIBRIUM. B. Spriet MLM-1303(TR). December 6, 1965. 18 p.
Translated by J. E. Selle (Monsanto Research Corp., Mound Lab., Miamisburg, Ohio) from the Journal of Nuclear Materials, Vol. 16, pages 59-67. An. abstract of the original article appeared in the Plutonium Abstracts, Vol. 5, Abstract No. 1113, July 30, 1965.
1795. NINETEENTH METALLOGRAPHIC GROUP MEETING, HELD APRIL 20-22, 1965 AT THE OAK RIDGE NATIONAL LABORATORY, OAK RIDGE, TENNESSEE. R. J. Gray, compiler ORNL-TM-1161. February 1966. 287 p.
A Special Metallographic Technique for Plutonium-Electrolytic Swab Etching. R. L. Greeson, W. L. Johns, R. J. Jackson. p. 45-54.
A metallographic technique employing electrolytic swab etching for the structural delineation of plutonium and
(Cont'd) -20-
Metallurgy and Ceramics (Cont'd)
1795. (Cont'd) its alloys is described. Also presented is a discussion of the etching solutions and conditioni along with photographic results which indicate the applicability of the method. (auth.)
Metallographic Examination of Highly Alpha-Contaminated Materials. G. A. McCaskey. p. 85-97.
Techniques were developed to metallographically examine, in a "clean" laboratory area, transuranium-aluminum alloys and other metal alloys contaminated with up to 2 x 109 d/m alpha activity. Metallographic specimens are prepared in a glove box and then removed in plastic bags containing 0.004-inch-thick polyvinyl chloride windows wetted on the inside and outside surfaces with immersion oil. By aligning ... the specimens in the windows, metailographic examinations and photomicrographs of microstructures can be made at magnifications up to 150Ox. (auth.)
A Metallographic Hot-Stage for Plutonium. R. L. Greeson, W. L. Johns, R. J. Jackson. p. 146-57.
A high-vacuum, hot-stage microscope suitable for use with plutonium is described. Excerpts from movie films of the alpha + beta and beta+alpha trans formation on high purity plutonium are also presented and discussed. (auth.)
1796. PREPARATION, COATING, EVALUATION, AND IRRADIATION TESTING OF SOL-GEL OXIDE MICROSPHERES. R. G. Wymer, J. H. Coobs (Oak Ridge National Lab., Oak Ridge, Tenn.) ORNL-P-1725. September 27, 1965. 43 p.
Microspheres of Th02, Pu02, Th02-U02, Th02-Pu02, rare earth oxides, and americium and curium oxides were prepared by sol-gel techniques. Sphere forming was accomplished by dispersing sols in 2-ethyl-1-hexanol containing appropriate surfactants or adulterants. Engineering feasibility of microsphere forming was demonstrated using a variety of sol dispersing techniques. Sol-gel microspheres, because of their sphericity and uniform size, are well suited ta coating in fluidized beds. Irradiation results indicate that carbon-coated oxide microspheres will be satisfactory fuels for high-temperature, gas-cooled reactors. 16 references. (auth.) -21-
Metallurgy and Ceramics (Cont'd)
1797. PROGRESS RELATING TO CIVILIAN APPLICATIONS DURING DECEMBER, 1965. Russell W. Dayton, Stan J. Paprocki (Battelle Memorial'.Institute, Columbus, Ohio) · BMI-1754. January 1, 1966. 31 p.
The following sections of this report contain information about plutonium: development·of BeO-Th02-Pu02 fuels, synthesis and fabrication studies of UN-PuN, measurements of selected physical properties of nitride fuels, UN-PuN compatibility studies, thermal irradiation studies of · nitride fuels, fuel-particle studies, and compatibility studies of carbon-coated plutonium fuel.
1798. SLIP IN ALPHA PLUTONIUM. S. E. Bronisz, R. E. Tate (Los Alamos Scientific Laboratory, Los Alamos, N. Mex.) LA-DC-7545. 1965. 10 p.
The determination of the slip systems operative in alpha plutonium has been started. The initial results indicate that slip planes near (114), (213) and (323) probably are operative at room temperature. The possibility that other pranes may also operate has not been eliminated. No evidence has been found that (020) is a very important slip plane. (auth.)
1799. THE SOLUBILITIES OF SELECTED ELEMENTS IN LIQUID PLUTONIUM. VII. NIOBIUM. D. F. Bowersox, J. A. Leary (Los Alamos Scientific Lab., Los Alamos, N. Mex.) LA-3436. February 11, 1966. 15 p.
The solubility of Nb in liquid Pu has been measured over the temperature range 700' to 1000'C. The solubility increased from 0.43 percent (by weight) Nb at 700'C to 1.48 percent Nb at 1000'C. The data fit the equation N log Nb - 0.2771 - 2.183 x 103 T-1, where NNb is the solubility expressed as the mole fraction and T is the temperature in degrees Kelvin.
The solubility of Nb in liquid alloy, which initially was 49.3 parcent (by weight) Pu, 40.8 percent Ce, and 9.9 percent Co, was measured from 500' to 900'C. The solubility increased from 0.053 percent (by weight) Nb at 500'C to 0.55 percent Nb at 900'C. The data fit the equation log XNb = -0.152- 2.243 x 103 T-1, where X is the solubility expressed as the mole fraction and T i bthe temperature in degrees Kelvin. 11 references (auth.) -23-
Metallurgy and Ceramics (Cont'd)
1803. STUDY OF U-Pu-Fe ALLOYS (MASURCA CRI.TI CAL EXPERIMENT) . Pierre Barthelemy, Rene Boucher (C.E.A.,.Cadarache, France) EUR FNR-17F. . July 1965. 40 p.. ANL-TRANS-224. 1965. 44 p.
These English translations. are of CEALR-2792.
An abstract of the French document appeared in Plutonium Abstracts, Vol. 5, No. 10, Abs. No. 4439. November 30, 1965.
1804. STUDY OF URANIUM-PLUTONIUM MONOXIDES. QUARTERLY PROGRESS REPORT, JULY.1- SEPTEMBER 30, 1965. R. L. Forbes, N. Fuhrman (United Nuclear Corp., White Plains, N.Y.) J., Andersen, K. Taylor (Carborundum Co., Niagara Falls, N.Y.) UNC-5138. (n.d.) 45 p.
Uranium-plutonium monoxide-type compositions stabilized with carbon, (UPu) (OC) , were synthesized by carbon re- duction of mixed U02 and Pu02 in helium and vacuum. Materials containing as high as 85 w/0 of a (UPu) (QC) 4 composition were produced with oxygen atom fractions as high as 0.56. Carbon-stabilized and nitrogen-stabilized uranium-plutonium monoxides, (UPu) (OCN) , were synthesized ;; by the uranium metal and carbon reduction routes in helium and vacuum. Essentially single-phase compositions were obtained having oxygen atom fractions as high as 0.36.
Specimens containing (UPu) (OCN) compositions were subjected to water corrosion tests. A.material containing 91 w/0 of 06.9 Puo .1)(OD .21(0 .3'7No .42) was intact after exposure to boiling water for 137 ht, but is disintegrated in 550'F water. (auth.)
1805. THERMAL EXPANSION OF COPRECIPITATED (U,Pu)02 POWDERS BY X-RAY DIFFRACTION TECHNIQUES. J. Roth, E. K. Halteman (Nuclear Materials and Equipment Corp., Apollo, Pa.) NUMEC-2389-9. October 1965. 67 p.
A high temperature X-ray powder diffraction study has been made of the (U, Pu)02 system over the. entire composition range using a high temperature, high vacuum diffractometer. An internal standard, thoria, was used for temperature determination. The compositions studied were 5, 12.5, 20, 35, 50, 80, and 100 w/0 PuO2,·and'pure UO2· 14 references. -22-
Metallurgy and Ceramics (Cont'd)
1800. SOME OBSERVATIONS ON THE COMPRESSIVE CREEP BEHAVIOR OF A DELTA STABILIZED PLUTONIUM - 1 W/0 GALLIUM ALLOY. Jack L. Robbins, Alan D. Wheeler (Lawrence Radiation Lab., University of California, Livermore, Calif.) UCRL-14489. October 8, 1965. 26 p.
The compressive creep characteristics of a plutonium - 1 w/0 gallium alloy were evaluated at a constant stress ' of 2000 psi over the temperature range 234'C to 387'C. In all cases the true strain versus time curves manifested a predominantly tertiary type of behavior. This accelerating creep rate was not caused by internal cavity formation; rather, it was related to partial recrystallization and possibly an enhancement in the recovery processes. The apparent activation energy for creep was determined to be 33.7 2.5 kcal/mole independent of strain between strain values of 0 and 0.15. 19 references. (auth.)
1801. SPECTROPHOTOMETRIC DETERMINATION OF GALLIUM IN PLUTONIUM- GALLIUM ALLOY. C. E. Pietri, A. W. Wenzel (U.S.A.E.C., New Brunswick Lab., New Brunswick, N.J.) NBL-228. November 1965. 7 P.
Macro amounts of gallium in plutonium-gallium alloys have been determined by an improved rhodamine B chlorogallate- benzene extraction-spectrophotometric method. The alloy is dissolved in hydrochloric acid, converted to the nitrate, and separated from the gallium and impurities by adsorption on Dowex-1 anion resin in 8N HN03. After dilution to the optimum concentration range the effluent is used for the gallium determination and an emis8ion spectrographic impurity analysis. The plutonium is assayed after its elution from the resin bed. The relative standard deviation was within 2. 2% for samples in the 3-15 ug. gallium range with no apparent bias. Analyses of alloy samples for gallium, plutonium, and impurities gave material balances of 100.1 0. 2%. (auth.)
1802. STUDIES ON THE EQUILIBRIUM TEMPERATURE FOR THE PLUTONIUM ALPHA- BETA TRANSFORMATION. J. W. Anderson (Los Alamos Scientific Lab., Los Alamos, N. Mex.) LA-DC-7278 (SUPPL.). (n.d.) 14 p.
This supplement presents an additional chart on the transformation and also discusses some effects of purity, thermal history and shape on the behavior of Pu specimens. LA-DC-7278 gave 117.0 0.5'C for the·equilibrium temperature for the alpha-beta transformation. It appeared in Plutonium Abstracts, Vol. 5, Abs. No. 1543, December 31, 1965. -24-
Metallurgy and Ceramics (Cont'd)
1806. TRANSFORMATION RATES OF PLASTICALLY DEFORMED PLUTONIUM. R. D. Nelson (Battelle Memorial Institute, Pacific Northwest Lab., Richland, Wash.) BNWL-203. March 1966. 13 p.
Plastic deformation of the stable beta phase in plutonium retards the B+a transformation. This is consistent with known martensitic transformations. There are in- sufficient dislocations in plastically deformed alpha to retard a +B transformation, but sufficient dis- locations are present to accelerate it. Deformed alpha plutonium can be annealed at 105'C. 15 references. (auth.) -25-
Miscellaneous
1807. FABRICATION COSTS FOR PLUTONIUM FUEL ELEMENTS. PART D: VARIABLE COST OF.FABRICATING U02-Pu02 FUEL ELEMENTS FOR THE PLUTONIUM RECYCLE TEST REACTOR. C. H.· Bloomster (Battelle Memorial Institute, Pacific Northwest Lab., Riehland, Wash.) BNWL-131D. 'October 1965. 22 p.
The variable (shop) cost of fabricating the HPD fuel element for the PRTR is.$113/kg of fuel (as oxide) or a unit cost of $3900 per fuel element·. The costs are based on the fabrication of the first 24 fuel elements by the pneumatic impaction-vibrational compaction processes. The shop labor requirements for each fuel element are 113 man-hours direct labor and 44 man-hours indirect labor. The variable costs include direct materials, some processing costs for nuclear materials, shop labor, direct overhead, and consumable supplies but do not include the cost of nuclear materials themselves, use charges, administrative overhead, research, develop- ment, or engineering costs.
Each fuel element contains 19 fuel rods and 34.6 kg of natural U02-2 wlgo Pu02 fuel. The fuel rudb are 170 elli long and 1.4 cm OD with 0.76 mm Zircaloy-2 cladding. The fuel length is 149 cm, and an 18 cm plenum extends above the fuel. A depleted U02 pellet is placed on each end of the fuel column. The fuel is held in place by an Inconel spring in the plenum. (auth.)
1808. PROSPECTIVE DEVELOPMENTS AND ECONOMICS OF NUCLEAR POWER GENERATION. B. B. Baturov, N. M. Sincv Soviet Atomic Energy, Vol. 18, No. 2: 191-209. February 1965.
The use of plutonium in thermal reactors is discussed. 14 references. -26-
Physics
1809. ACCELERATION OF HEAVY IONS AND THE PREPARATION OF HEAVY ELEMENTS. F. Smend (University of Gottingen, Germany) Naturwibsenschaften, Vol. 52, No. 23: 632-5. December 1965.
In German. This review article describeds the production of element 104 from Pu-242, and gives some of the properties of element 104. The production of Pu-239 from U-238, the production of Cm-246 from Pu-239 and the production of Cm-242 from Pu-239 are also described. 17 references.
1810. THE ANGULAR ANISOTROPY OF FISSION BY SUB-BARRIER DEUTERONS. Yu. A. Nemilov, Yu. A. Selitsku, S. M. Solov'ev, V. P. Eismont Yadernaya Fizika, Vol. 2: 460-65. September 1965.
In Russian. Nuclear Science Abstracts, Vol. ·20: Abs. No. 3122. January 31, 1966. Chemical Abstracts, Vol. 64: Abs. No. 2946f. January 31, 1966.
1811. ANGULAR DISTRIBUTIONS ON NEUTRON FISSION FRAGMENTS OF Th-230, :.... Pu-238 AND Am-241. P. E. Vorotnikov, S. M. Dubrovina, V. A. Shigin, G. A. Otroshchenko ANL-TRANS-242. October 1965. 15 p.
Translated from report IAE-817, by E. K. Wilip.
The cross-section of Pu-238 fission by neutrons with energy from 50 to 1400 kev were measured. The angular distributions of fission fragments were recorded by four thin ionization chambers. The differential cross-section of Pu-238 neutron fission can be described by a ee) = a (90') (1+ a cos20), and the measurement results are graphed. A formula and graph of results are given for the total fission cross- section. .The data obtained were used for a K-band analysis of Pu-238 fission cross-section. At neutron energy above 800 kev the total fission cross-section of Pu-238 remains constant and equal to 2.8 * 0.3 barns. This leads to a ratio of the fission and neutron widths -2.6 for the Pu-239 nucleus at the excitation energy -1 mev above the fission threshold. 24 references. -27-
Physics (Cont'd)
1812. CHARACTERISTICS OF ASYMPTOTIC SPECTRUM OF NEUTRONS IN URANIUM. A. A. Malinkin, F. Nasyrov, V. F. Kolesov Soviet Atomic Energy, Vol. 18, No. 2: 225-27. February 1965.
The reaction cross sections were determined relative to the fission cross section of Pu 239 Direct measurements were also.made of the neutron spectrum in the region up to 0.95 MeV.
1813. THE COMPOSITION OF TRANSURANIUM-ELEMENTS. C. Keller (Gesellschaft fur Kernforschung mbH, Karlsruhe, Germany) Atompraxis, Vol. 12, No. 1: 13-23. January 1966. In German. Experimental techniques are described ·for the build-up of transuranium elements. It can be deduced that weighable amounts of the transuranium elements up to fermium can be prepared only by long-time irradiation of uranium or plutonium in high flux reactors: Nuclear reactions with heavy ions and - to a smaller extent - nuclear explosions appear to be most promising for the synthesis of new trans- curium elements and isotopes. Since these heavy ion nuclear reactions have extremely small cross-sections, only tracer quantities or even few atoms of the elements with Z > 100 will be produced. On account of the systematics of their formation and disintegration it must be expected that the heaviest nuclides have only very short half-lives. There- fore they can presumably be identified only indirectly by physical methods. 36 references. (auth.)
1814. ENERGY LEVELS OF Pu 3+ IN LANTHANUM TRICHLORIDE. John G. Conway, K. Rajnak (Lawrence Radiation Laboratory, University of California, Berkeley, Calif.) Journal of Chemical Physics, Vol. 44, No. 1: 348-54. January 1, 1966.
Polarized absorbtion spectra and some Zeeman effect measure- ments in the region of 20,000-32,000 cm-1 are reported for Pu3+ in LaC13· A total of 25 J levels was fitted with an rms deviation of 100 cm-1 with the parameters values 0 = .14,930.5, El = 3726 ..7, E2 = 14.99, E 3 = 350.18, 4 = 2260.2, a =.36.5, B = -1171. The large values of
a and B indicate that configuration-interaction effects cannot be neglected in an analysis of the spectra of the higher actinides. (auth.) -28-
Physics (Cont'd)
1815. A FEASIBILITY STUDY OF THE METHOD OF NON-DESTRUCTIVE ASSAY OF U-235 AND Pu-239 IN IRRADIATED FUEL SLUG. (Atomic Energy Establishment, Trombay, India) NP-15688. September 1965. 114 p.
A method for the estimation of U-235 and Pu-239 concentrations in irradiated samples is presented, using a slowing down time lead spectrometer and making use of the difference in fission cross section of U-235 and Pu-239 in the 0.1 to 1 ev region. 17 references.
1816. FISSION BY A RADIATIONLESS TRANSITION IN THE U MESONIC ATOM 239 PU. V. Cojocaru, L. Marinescu, M. Petrascu, G. Voiculescu (Institute of Atomic Physics, Bucharest, Rumania) A. Ignatenko, M. Omelianenko (Joint Institute for Nuclear Research Dubna, USSR) Physics Letters, Vol. 20, No. 1: 53-55. January 15, 1966. JINR-D-2427. 1965. 8 P.
The time distribution of fission in the U-mesonic atom 239 pu was measured. It was found that the ratio prompt e. fissions/fissions by U-capture is equal to 0.43 * 0.09.
This value indicates a radiationless.transition contribution t, by an order of magnitude greater than in uranium and thorium. 11 references. (auth.)
1817. GAMMA RADIATION FROM Pu241. I. A. Baranov, V. V. Berdikov, A. S. Krivokhatskil A. N. Silant'ev Bulletin of. the Academy of Sciences of the USSR, Physical Series, Vol. 29, No. 1: 161. 1965.
The spectrum of y rays from Pu 241 in coincidence with the y particles is reproduced. The values obtained for the absolute intensities of the 95 and 145 keV y rays are 51 + 5 and 7.5 + 1%.
1818. MEASUREMENT OF THE ABSOLUTE VALUE OF ETA FOR U-233, U-235 AND Pu-239 USING MONOCHROMATIC NEUTRONS. J. R. Smith, S. D. Reeder, R. G. Fluharty (Phillips Petroleum Co., Ato*ic Energy Division, Idaho Falls, Idaho) IDO-17083. February 1966. 45 p.
The absolute value of eta, the number of fission neutrons per absorption, has been measured for U-233, U-235 and Pu-239, using monochromatic neutrons from a crystal spectrometer.
(Cont'd)
______1 -29-
Physics (Cont'd)
1818. (Cont'd) Measurements were made on all' three isotopes at 0.025 eV neutron energy, and on U-233 and Pu-239 at 0.057 eV. The Bragg beam from Be (0002) was passed through a mechanical monochromator to remove'higher order neutrons and yield a truly monochromatic beam. The neutron detector was a manganous sulphate bath, which absorbed in 'turn the Bragg beam and then the fission neutrons produced when the beam was completely absorbed in a fissionable sample. The ratio of the levels of Mn-56 activities produced in the two types of irradiation yielded the value of eta for the fissionable material of the sample, after the application of. a few small corrections. The method of least squares was used to extract the values of eta from the experimental data. These values are at 0.025 eV: for U-233, 2.298 i 0.009; for U-235, 2.079 + 0.010; for Pu-239, 2.108 + 0.008. At 0.057 eV: for U-233, 2.288 0.009; for Pu-239, 2.034 + 0.009. 19 references. (auth.)
1819. A NUMERICAL STUDY OF THE METHOD OF WEIGHTED RESIDUALS. G. C. Pomraning (General Atomic, San Diego, Calif.) Nuclear Science and Engineering, Vol. 24, No. 3: 291-301. March 1966.
The variational method and region-balance method, both special cases of the more general method of weighted residuals, are each used as the formalism to develop a spatial expansion of the diffusion equation for two problems. These are 1) a spatially dependent spectrum problem for the.purpose of computing the self-shielding in the 240 Pu resonance and 2) a simple one-dimensional eigenvalue problem. In both instances numerical results indicate that the variational method is more accurate than the region-balance method. Of particular interest is the variational spatial-expansion approach to the eigenvalue problem. This may be a useful method for deriving a set of difference equations for the multi- group diffusion equation in that it should lead to an accurate representation of the flux with a relatively small number of mesh points. 12 references. (auth.)
1820. PHOTOFISSION OF EVEN-EVEN NUCLEI NEAR.THE.THRESHOLD. N. S. Rabotnov, G. N. Smirenkin, A. S. Soldatov, L. N. Usachev, S. P. Kapitsa, Yu. M. Tsipenyuk ANL-TRANS-245. (n.d.) 28 p.
A detailed measurement of the angular distributions of photofission fragments at excitation energies of the order of 6 mev· and below for Th232, U238 and Pu24O was carried out. -30-
Physics (Cont'd)
1821. PHYSICS DEPARTMENT PROGRESS REPORT, FEBRUARY-MAY, 1965. A. Lorenzi ed. (University of California, Lawrence Radiation Lab., Livermore, Calif.) UCRL-14360. (n.d.) 107 p.
N.eutron scattering from resonances in Pu-239. p. 44. - · Magnetic properties of.K02, Pu02·,· NiSe, NiS, and FeTeo .95. p.· 47-48.
1822. ON THE PROPAGATION OF RESONANCE NEUTRONS IN URANIUM. Yu: Ya. Stavisskii L. E. Sherman Atomnaya Energiya, (U.S.S.R.), Vol. 19:·292-94. September 1965.
In Russian. · ' Nuclear Science Abstracts, Vol. 20: Abs. No. 3031. January 31, 1966.
1823. PULSED HIGH INTENSITY FISSION.NEUTRON SOURCES. (U.S. Atomic Energy Commiss,ion, Washington, 'D. C.) CONF-650217. February 1965. 147 ·p.·
Sub-Critical Neutron Amplifier Systems. R. G. Fluharty. :..': p. 11-.24. An accelerator driven,, Pu fueled neutron amplifier is proposed. The pulsed operation would be used for time of flight experiments. Four tables showing comparisons with other pulsed neutron systems are given.
1824. RESEARCH LABORATORIES SEMI-ANNUAL REPORT FOR THE PERIOD JULY-DECEMBER 1963. (Israel Atomic Energy Commission, Yavne, Israel) IA-920. (n.d.) 196 p.
Nuclear Science Abstracts, Vol. 20: Abs. No. 2520. January 31, 1966.
1825. STUDY OF THE NEUTRON MODERATION PROCESS IN BERYLLIUM AND BERYLLIUM OXIDE BY THE PULSE METHOD. I. F. Zhezherun Soviet Atomic Energy, Vol. 18, No. 2: 158-66. February 1965.
A plutonium chamber enclosed in a screen of a mixture of samariam and gadolinium oxides was used as a pulse detector for neutrons with energy 0.3 eV. Measured and calculated values of the moderation time at this energy among others, is given for Be and BeO. 29 references. -31-
Physics (Cont'd)
1826. A STUDY OF THE "384" KeV COMPLEX GAMMA EMISSION FROM Pu-239. 5 R.'S. Forsyth, N. Ronqvist (Aktiebolaget AtoAenergi, Stockholm, Sweden) AE-202. November 1965. 15 p.
The present paper describes gamma spectrometric studies of plutoniwn 'sainples of several isotopic compositions using a sodium iodide detector and a lithium-drifted germanium detector. The 384 KeV peak has been shown to be a complex peak containing 12 gamma components due to plutonium-239· between 300 - 450 'KeV, and their relative intensities have been estimated. Anion exchange and solvent extraction experiments have also demonstrated that two further contributions due to uranium-237 are present in plutonium containing significant amounts of plutonium-241.. (auth.)
1827. A 12 GROUP SET OF PHOTON CROSS SECTIONS FOR USE IN ANISOTROPIC Sh CALCULATIONS OF PHOTON TRANSPORT. W. M. M. Kerr, K. Parker, D. V. J. Williams, Patricia M. Wilton (Atomic Weapons Research Establishment; Aldermaston, U.K.) AWRE-0-79/65. October 1965. 38 p.
Tile 12 group set 2 phoron cross Sections talculated for use in·STRAINT and other programs in which anisotropic scattering··can be taken into account is described. Three pages of data are .included for plutonium.
' ; -32-
Reactor Technology
1828. ADVANCED BERYLLIUM OXIDE CONCEPTS. PROGRESS REPORT, JANUARY 1- MARCH 31, 1963. .,(General Atomic, San Di.ego, Calif.) GA:4165. May 244 1963. 68 p.
Plutonium Reactors, p. 31-66. Preliminary work on the possiblity of using plutonium with beryllium oxide in low-power output applications is described in this report. Work has been concentrated in the power output range below 100 Mw(t) and it has been found,that practical reactor designs using metal-clad Pu02/BeO fuel appears to have some attractive characteristics. Calculations indicate that the combination of Pu239, 240 241 PU , and PU in the fuel can lead not only to long burnup lifetimes with a given fuel loading, but also the intimate mixture of moderator with the fuel provides a very large prompt negative moderator temperature co- efficient, resulting in very stable plant operating conditions. Areas requiring further.research and develop- .ment are discussed in this report. 16 references. (auth.)
1829. - ON THE BURN-UP CHARACTERISTICS·OF LARGE Pu-U FAST REACTORS. Hiroshi Nishihara, Masao Ohta (Kyoto University, Kyoto-shi, Japan) Journal of Nuclear Science and Technology, Vol. 2, No. 12: 525-31. December 1965.
Breeding ratio, effective multiplication factor keff and sodium- void reactivity effect of Pu-U fast reactors having a 3,000 1 core volume are investigated as functions of burn-up. Following results are obtained: (1) Initial breeding ratio does not fail to be a measure for roughly estimating breeding character. (2) By charging Pu fuel in the internal blanket situated inside core region, keff of the system remains almost constant along with burn-up. (3) The variation of sodium-void reactivity due to fuel burn-up of the above system does not seem to· be serious. (auth.)
1830. · . CONCEPTION OF Tlir EUROCHEMIC PLANT AND ITS ROLE IN THE START- -UP,, QF EUROPEAN FUEL CYCLES. T: J. Barendregt, R. Rometsch (Eurochemic Co., Mol, Belgium) · Atompraxis, Vol. 12,.No. 1: 25-29. January 1966.
Eurochemic will be able to reprocess the irradiated fuels discharged from the reactors of its thirteen member countries.
(Cont'd) -33-
Reactor Technology (Cont'd)
1830. (Cont'd) Chemical decladding methods have been adapted and developed to cope with aluminum, magnesium, stainless steel and zirconium. Type claddings and Purex type flowsheets have been developed to deal with a variety of uranium fuels of enrichments from natural to 93% 235U. Thus a flexible multi-purpose plant has been designed and constructed and is now being tested. It employs pulse columns for the main extraction' cycles and mixer-settlers for final purification of plutonium and highly enriched 'uranium. The design throughput is about 5 kg H/day for the highest enrichment and 400 kg U/day for power reactor fuels of enrichments less than 5% 235u For these fuels the capacity can easily be extended to more than 1000 kg U/day. In the next five years, there will be a $25 million worth recovery of uranium and this value can be realised either by re- enrichment in a US diffusion plant or by up-grading by means of blending in Europe and recycling the blended material through suitabld reactors. The recovered plutonium will be wbrth at least $9 million and can be used in development work for fast breeder reactors or can be recycled to thermal reactors. Eurbchemic will open several possibilities for fuel cycles in Europe, but much coordination is still needed between the different reactor operators and fuel fabricators in various countries. (auth.)
1831. CONTROL OF REACTIVITY IN HIGH CONVERSION RATIO: PLUTONIUM FUELED, THERMAL POWER REACTORS. G. Srikantiah (Brookhaven National Lab.,. Upton, N. Y.) BNL-8748. December 1964. 35 p.
Methods of long-term reactivity control for plutonium fueled, D20 moderated reactors are considered which favor high conversion ratios. One method uses annular gaps around the fuel elements which can be selectively filled with the D20 moderator. Reactivity compensations ranging from 8- 15% can be achieved with gaps of 6-8 c m thickness and a corresponding reduction in conversion ratio of 3 - 5%. In the second method depleted uranium sleeves are utilized around fuel elements in annular regions of the reactor which can be removed as required during long-term operation. Sleeves of only· 0.2 cm thickness around fuel elements in the·central region of the reactor provide reactivity compensations 'of up to 10% and actually increase the conversion ratio in. the · design studied.
(Cont'd) -34-
Reactor Technology (Cont'd)
1831. (Cont'd) Average conversion ratios in a large D20 cooled and moderated reactor using Zircaloy pressure tubes of about 0.90 are obtained at fuel burn up of 104 MWD/T. The average conversion ratios would increase to about 0.97 if beryllium based pressure tubes could be developed. 21 references. (auth.)
1832. DEVELOPMENT AND TESTING OF U02- Pu02 FAST REACTOR FUELS. PROGRESS REPORT, JULY 1-SEPTEMBER 30, 1965. (Nuclear Materials and Equipment Corp., Apollo, Pa.) NUMEC-3524-8. November 22, 1965. 32 p.
The required quantity of the mechanically mixed U02-20 w/0 Pu02 Powder has been produced and fully characterized. Sintering trials for this powder are now being performed. Comparison by electron microprobe shows that coprecipitated U02-15 w/0 Pu02 has better homogeneity than mechanically mixed fuel, although the latter is quite good. Physical property measurements are being made of the mechanically mixed fuels.
1833. EXPERIMENTAL STUDIES OF TRANSIENT EFFECTS IN FAST REACTOR FUELS. SERIES II. MIXED OXIDE (Pu02-U02) IRRADIATIONS. J. E. Hanson, J. H. Field, S. A. Rabin (General Electric Co., Advanced Products Operation, San Jose, Calif.) GEAP-4804. May 1965. 96 p.
The results of an experimental program to evaluate the performance of non-pre-irradiated fast ceramic reactor fuel under conditions simulating accidental power ex- cursions are presented. Results from three experiments in the ·TREAT facility using 0.250-inch-0.d., Type 347 stainless steel clad, 20 weight percent Pu02-80 weight percent U02 fuel specimens are interpreted with regard to fuel-cladding temperatures, fuel vapor pressure, thermal expansion of the fuel, and cladding integrity. Incipient failure limits for axially-unrestrained fuel are identified as functions of the maximum fuel and cladding temperatures attained during the transient. 23 references. (auth. -35-
Reactor Technology (Cont'd)
1834. FAST POWER REACTORS. 0. D. Kazachkovsky (Institute of Atomic Reactors, Melekess, USSR) V. B. Lytkin (Physics and Power Institute, Obninsk, USSR) Atomic Energy Review, Vol. 3, No..4: 47-87. 1965.
This paper deals with questions related to the development of nuclear power on a large scale, such as can be obtained only through the use of fast reactors., .The basic physical characteristics of fast power·reactors are considered: high breeding ratios, high power density in the core, high.concentration of fissile.material, use of a liquid- metal coolant. The various types of fuel that can be used and possible methods of its chemical reprocessing are reviewed. The economic characteristics of fast power reactors are considered together with possible means of further improving them. 80 references. (auth.)
1835. FFTF DRIVER FUEL: PU02-STAINLESS STEEL.CERMET. W. J. Bailey, R. J. Hennig, D. R. deHalas, R. E. Skavdahl (Battelle Memorial Institute, Pacific Northwest Lab., Richland, Wash.) BNWL-SA-251. November 3, 1965. 26 p.
The proposed design and operating conditions for the cermet fuel elements. are summarized in tables.
1836. GERMAN WORK ON FAST REACTORS. Nuclear Engineering, Vol. 11, No. 117: 106-7. February 1966.
There is a short discussion of German calculations of the reactivity value of plutonium.
1837. HIGH PERFORMANCE U02 PROGRAM. QPR NO. 17, APRIL-JUNE 1965. M. F. Lyons, ed. (General Electric Co., Atomic Power Equipment Dept., San Jose, Calif.) GEAP-3771-17. July 15, 1965. 95 p.
Fission Product and Heavy Element Distributions in High Performance U02 Fuel Rods. J. H. Davies, R. F. Boyle, J. F. Hanus. p. 6-1 to 6-12. Post-irradiation radial and axial distribution of fission products and heavy elements (uranium and plutonium) in a High Performance U02 fuel rod, which operated with gross central melting during irraditaion, was analysed. Homogenization indicates mixing from convection in the molten zone and confirms earlier, heat-transfer-derived evidence of molten fuel convection.
(Cont'd) -36-
Reactor Technology (Cont'd)
1837. (Cont'd) There is a general correspondence between the alpha autoradiggraph characteristics and variations, and analytical measurements of the heavy element concen- trations and distributions.
1838. Nl ICI,EAR DESIGN OF MPBE. W. H. Hannum (Los Alamos Sci6ntific Lab., Los Alamos, N. Mex.) LA-DC-7475. 1965. 18 p.
The design of a Molten Plutonium Burnup Experiment which will be used to determine the properties of a molten plutonidn· fuel during and after high burnup is described. A brief review of the large reactor design concept is included. The MPBE will investigate the range of burnup 6 capability of 10%, with power densities of 1.3 to 2 Mw/liter fuel. This design appears to have adequate control, very favorabfe reactivity coefficients, and conservative thermal design. The more important properties of this core are summarized in a table.
1839. NUCLEAR FUELS AND MATERIALS DEVELOPMENT. William L. R. Rice, ed. (Fuels and Materials Development Branch, Div. of Reactor Development and Technology, AEC, Washington, D.C.) TID-11295 (Pt. 1, 4th Ed.). June 1965. 145 p.
This report is a summary of work being done under the Advanced Reactor Technology program at twenty three laboratories. The entries below contain information about plutonium.
Argonne National Laboratory: sintering of UC-PuC, plutonium monosulfide, thorium and plutonium phosphides, thorium- uranium-plutonium fuel alloy development, and irradiation behavior of vibratory-compacted UC-PuC.
Battelle Memorial Institute, Columbus Laboratory: plutonium compound technology.
Battelle Memorial Institute, Pacific Northwest Laboratory: plutonium-oxygen system, plutonium-nitrogen system, plutonium- carbon system, plutonium-boron system, and fast fuel develop- ment.
(Cont'd) -37-
Reactor Technology (Cont'd)
1839. (Cont'd) Monsanto, IRes.earch Corporation,,Mound Laboratory: phase transformations in high purity plutonium, phase studies of low melting plutonium alloys, .thermal diffusivity of uranium-plutonium carbides, properties of the liquid alloy plutonium- 1 Wt% gallium- physical properties of liquid plutonium-cerium-cobalt alloys, and preparation of microspheres of cermnic materials.
Nuclear Materials and Equipment Corp.: thermal expansion characteristics of coprecipitated (U,Pu)02 Powders, morphologital studies on (U,Pu)02 Powders, homogeneity of mechanically mixed U02-PU02 Powders, irradiation testing of U02-PU02 fuels, and growth of single crystals of plutonium.
United Nuclear Corp.: carbide fuel development: irradiation tests, and out of pile properties; study of uranium- plutonium monoxides: carbothermic reduction of oxides, and metal reduction of oxides.
1840. PLUTONIUM PRODUCTION AND BURNUP CALCULATION METHODS FOR LIGHT WATER MODERATED REACTORS. G. A. Sofer, A. H. Kazi, J. R. Tomonto, P. Buck (United Nuclear Corp., White Plains, N. Y.) Vienna, International Atomic Energy Agency, 1965, Preprint No. SM-67/42. 43.p. (CONF-650803-16). ORINS.
Nuclear Science Abstracts, Vol. 20: Abs. No. 3535. January 31, 1966.
1841. PLUTONIUM SUBCRITICAL EXPERIMENT PROGRAM. FIFTH QUARTERLY REPORT, JULY 1-SEPTEMBER 30, 1965. J. G. Carver (General Electric Co., Atomic Power Equipment Dept., San Jose, Calif.) GEAP-4965. October 1, 1965. 15 p.
Design of the core support system is complete, and the fuel rods are nearly complete.· Multiplication factors have been calculated for lattices composed of Program fuel rods in room temperature water. -38-
Reactor Technology (Cont'd)
1842. REACTOR DEVELOPMEN'l' PROGRAM PROGRESS REPORT, SEPTEMBER 1965. (Argonne National Lab., Argonne, Ill.) ANL-7105. October 20, 1965. 93 p.
The following sections of this report contain information about plutonium: FARET criticals (ZPR-3), p. 18-20; general fabl-reactor fuel development-metallic fuels, p. 22-26, carbide fuel elements, p. 27-28, irradiation testing, p. 28-31, zero-power reactors, p. 31-32; general fast reactor fuel reprocessing development-pyrochemical processes, p. 34-35; experimental reactor and nuclear physics - nuclear constants, p. 38-40; theoretical reactor physics - effects of randomness on group cross sections, p. 40-41; high-temperature materials - ceramic fuel materials, p. 41-43, irradiation testing, p. 44-47; chemical separations - fluorination and volatility separations processes, p. 51-56; plutonium recycle reactors - EBWR plutonium recycle, p. 58.
1843. REACTOR DEVELOPMENT PROGRAM PROGRESS REPORT: OCTOBER 1965. (Argonne National Lab., Argonne, Ill.) ANL-7115. November 23, 1965. 86 p.
The following sections of this report contain information about plutonium: Faret-reference Core I design, p. 17-21; General fast reactor fuel development-metallic fuels, p. 31-33; General fast reactor physics - ZPR-6, p. 27-28, ZPR-9, p. 29-30; General fast reactor fuel reprocessing development - processes for future fast reactor fuels, p. 38-40; Theoretical reactor physics - effects of randomness on group cross section, p. 44-45; High-temperature materials studies - ceramic fuel materials, p. 49-55, irradiation of materials for fast reactors, p. 56-59; Chemical separations - fluidization and volatility separations processes, p. 64-65; Plutonium recycle program, p. 66-67.
1844. REACTOR DEVELOPMENT PROGRAM PROGRESS REPORT. JANUARY 1966. (Argonne National Lab., Argonne, Ill.) ANL-7152. February 24, 1966. 98 p.
The following sections of this report contain information about plutonium: EBR-II - experimental irradiations, p. 6-7; General fast reactor physics - ZPR-3, p. 8-14, ZPR-9, p. 19-21; General fast reactor fuel development - zero-power reactors, p. 24-33, metal fuels, p. 33-34, irradiation testing, p. 36-41, development of Nupac- type fuel elements, p. 41; High-temperature materials studies - ceramics, p. 55-57, irradiation testing, p. 57-58;
(Cont'd) -39-
Reactor Technology (Cont'd)
1844. (Cont'd) Chemical separations - fluidization and volatility separations processes, p. 66-70; Chemical and associated energy-transfer problems in reactor safety - interaction of fuel and cladding with liquid sodium, p. 90-96.
1845. REPROCESSING STUDIES AT KJELLER. W. Kraak (Institutt for Atomenergi, Kjeller, Norway) EuroNuclear, Vol. 3, No. 2: 80-83. Febtuary 1966.
The work being done at the ND and Silex pilot plants, the testing station, and in laboratory research is described.
1846. SIMULATION OF Pu-239 FUELED CORES BY MEANS OF Pu-239 - U-235 FUELED CORES IN FAST CRITICAL ASSEMBLIES. A. Ancarani (Kernforschungszentrum, Karlsruhe, West Germany) EUR-2474e. December 8, 1964. 100 p.
The author studied a zoned reactor, the central part of which has the exact Pu composition of the reactor under study, while the surrounding zone (driver) is made up with fuel of different composition·- these fissile isotopcs boing Pu-239, or more likely, U-235. The problems studied were the maximum size of the reactors which it is possible to simulate with given quantities of Pu, and the reliability on flux spectrum, for physical measurements, of the zoned reactors in comparison with that of the full scale ones.
1847. U02-Pu02-Zr02 FUEL DEVELOPMENT PROGRAM. .QUARTERLY PROGRESS REPORT JULY 1, 1965-SEPTEMBER 30, 1965. (Nuclear Materials and Equipment Corp., Apollo, Pa,) NUMEC-3505-8. October 21, 1965. 34 p.
Studies have continued to develop the U02-Pu02-Zr02 fuel system. This fuel system has potential application for plutonium recycling in present-day thermal reactors now fueled with slightly enriched uranium. The fuel compositions to be investigated. include 4, 6, 10, and 12 v/0 Pu02 and 25, 50, and 75 v/0 Zr02, the remainder being U02·
(Cont'd) ' -40-
Reactor Technology (Cont'd)
1847. (Cont'd) The enriched uranium ceramic powders from which pellets will be fabricated for the in-reactor testing were prepared by coprecipitation. Other experimental com- positions were prepared by mechanical blending. Test pellets of these were sintered to densities in excess of 90% of theoretical.
Thermophysical studies of the U02-PU02-Zr02 system were continued. X-ray crystallographic data have been obtained as part of the phase diagram studies. Preliminary data have been obtained for melting points, thermal expansion, thermal cycling stabilities, and air oxidation stabilities. Apparatus for thermal analysis studies is being built.
Design of the irradiation test pins and the irradiation test capsule was complete and major components for fabrication of the assembled capsule have been procured. (auth.)
1848. USE OF PLUTONIUM AS A FUEL IN NUCLEAR REACTORS. QUARTERLY REPORT NO. 5, JANUARY 1-MARCH 31, 1965. (Centre d'Etude de l'Edergie Nucleaire, Brussells, Belgium) EURAEC-1505. May 1965. 36 p.
Development of ceramic oxide fuel: Fabrication of the Venus and Vulcain rods, which is now in progress,. shows a marked improvement in the technique over the previous fabrication of BR-3/PWR rods. However, plutonium dis- tribution requires further improvement, primarily in the case of fuels which must satisfy specifications similar to those for elements with enriched U02 pellets. The welding tests showed that precautions should be taken when designing vibrated (or swaged) elements, where the weldability properties of the can are mediocre.
The results of contact radiography measurements based on plutonium 384 keV emission are strongly affected by transversal plutonium localization. Judging from present information, transversal plutonium distribution can produce a 20% measurement error for rods of internal diameter 12 mm. and a 10% error for rods of internal diameter 7.5 mm.
Plutonium reprocessing: It is especially important to cool the hydrochloric solutions when the samples are being prepared for purification on ion-exchanger columns. This operation prevents the formation of Pu VI, and con- sequently avoids big losses of fissile material.
(Cont·' d) -41-
Reactor Technology (Cont' d)
1848. (Cont'd) Physical and neutron study of the U02-Pu02-H20 lattices: Space-time measurements by the pulsed neutron method were effected on an Al-H20 lattice of adjustable size. 11 references. (auth.)
1849. USE OF PLUTONIUM AS A FUEL IN NIJCLEAR REACTORS. QUARTERLY REPORT NO. 6, APRIL 1-JUNE 30, 1965: (Centre d'Etude de l'Energie Nucleaire, Brussels, Belgium) EURAEC-1506. August 1965. 60 p.
Development of ceramic oxide fuels: Longitudinal plutonium distribution in the BR-3/Vulcain elements was improved by adapting the filling sequences. As decontamination of the elements was found to be a very long process, tests were initiated to decontaminate the stainless steel canned elements by electrolysis. To determine the oxygen content of the oxides by a dry method, hydrogen can be replaced by an Ar - 30% mixture. A method of determining chlorine was developed for measuring the chlorine content of the fuel rods.
Properties of fuels: The results obtained in the frame- work of research on heat transfer inside the fuel were confirmed at a meeting of experts.
Evaluation of fuels: Two sets of three vibrated samples were irradiated at low power in order to test the irradiation operating conditions and interpretation of the results. It was noted that the presence of the samples greatly dis- turbs neutron flux and requires densimeters to be in- corporated in the fuel or in immediate contact with it. Post-irradiation tests were effected without any special problems.
Physical and neutron study of the U02-Pu02-H20 lattices: Sub-critical tests in the k = 0.6 - 0.93 range were effected with elements from the THETIS reactor for an idealised lattice, similar,to that in the reactor. These measurements were taken by three methods: static inverse multiplication, the source extraction method, and the pulsed neutrons method. Initial analysis of the results shows satisfactory correlation between the three methods. (auth.)