Fox, C.H. Jr.
North Carolina State Univ., Raleigh (USA)1974
North Carolina State Univ., Raleigh (USA)1974
AbstractAbstract
[en] Fission products were injected into thorium disks by the fission recoil doping method at concentrations approximating infinite dilution. Tantalum-wrapped samples were isothermally annealed in an evacuated quartz-kimax tube at 872 to 11770C. Release of 133Xe was monitored during the anneal using a shielded gamma ray spectrometer. For nonvolatile fission products, the samples were sectioned after the anneal for concentration profile analysis using the electropolishing method. Diffusion of Te and Xe is consistent with the accepted theory of vacancy diffusion of substitutional solute impurities in fcc metals. Diffusion of Ba and Ce is close to that of self-diffusion in thorium but is inconsistent with the Lazarus--LeClaire theory. The mechanism is substitutional-interstitial with the substitutional phase dominant. A strong correlation was observed between the activation energy and valence for impurity diffusion in thorium. The fast diffusion observed for 99Mo is consistent with a substitutional-interstitial mechanism. A correlation exists between the ratio of the ionic radius for the impurity and host and the measured activation energy for impurity diffusion. Very low diffusion rates are indicated at the operating temperatures of the Unclad Metal Breeder Reactor. The diffusion of Mo will be the most significant of the fission products studied. (DLC)
Original Title
872 to 11770C
Source
1974; 240 p; University Microfilms Order No. 75-15,150.; Thesis (Ph. D.).
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Report
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Thesis/Dissertation
Country of publication
ACTIVATION ENERGY, ANNEALING, BARIUM 140, CERIUM 141, CERIUM 143, DIFFUSION, DOPED MATERIALS, FISSION PRODUCT RELEASE, FISSION PRODUCTS, INTERNAL CONVERSION RADIOISOTO, IODINE 133, MOLYBDENUM 99, TELLURIUM 132, TEMPERATURE DEPENDENCE, THORIUM REACTORS, THORIUM-ALPHA, VALENCE, VERY HIGH TEMPERATURE, XENON 133
ACTINIDES, BARIUM ISOTOPES, BETA DECAY RADIOISOTOPES, BETA-MINUS DECAY RADIOISOTOPES, CERIUM ISOTOPES, DAYS LIVING RADIOISOTOPES, ELEMENTS, ENERGY, EVEN-EVEN NUCLEI, EVEN-ODD NUCLEI, HEAT TREATMENTS, HOURS LIVING RADIOISOTOPES, INTERMEDIATE MASS NUCLEI, IODINE ISOTOPES, ISOMERIC TRANSITION ISOTOPES, ISOTOPES, METALS, MOLYBDENUM ISOTOPES, NUCLEI, ODD-EVEN NUCLEI, RADIOACTIVE MATERIALS, RADIOISOTOPES, RARE EARTH NUCLEI, REACTORS, TELLURIUM ISOTOPES, THORIUM, XENON ISOTOPES
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AbstractAbstract
No abstract available
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Secondary Subject
Source
Joint meeting of the American Nuclear Society and the Atomic Industrial Forum and Nuclear Energy Exhibition; San Francisco, California, USA; 11 Nov 1973; See CONF-731101-- Published in summary form only.
Record Type
Journal Article
Literature Type
Conference
Journal
Trans. Amer. Nucl. Soc; v. 17 p. 177-178
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Fox, C.H.; Davis, L.G.; Harder, C.R.; Shoolbred, K.C.
GA Technologies, Inc., San Diego, CA (USA)1984
GA Technologies, Inc., San Diego, CA (USA)1984
AbstractAbstract
[en] The US/Japan agreement provided for sharing of Doublet III experimental time between scientific teams from GA and the Japan Atomic Energy Research Institute (JAERI), and also provided for upgrading the experimental capabilities of Doublet III with additional power systems, plasma heating capability, and plasma diagnostic systems
Primary Subject
Source
Oct 1984; 159 p; Available from NTIS, PC A 08/MF A01; 1 as DE85003059
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Report
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Progress Report
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AbstractAbstract
[en] A study was performed of the diffusion in α-thorium of fission products representing impurity atoms with a diversity of size and valence differences with respect to the solvent lattice. The atoms were recoil injected into thorium disks. Diffusion coefficients were determined for 133Xe by monitoring its release during annealing, and for the other isotopes by post-annealing concentration profile analysis. The Arrhenius constants D0(cm2/sec), resp. Q(kcal/mole) were obtained for the diffusion coefficients where, D=D0 exp(-Q/RT);99Mo: 7.6 X 10-4 and 37.6; 132Te: 1.32 X 106 and 95.6; 133I: 2.7 X 10-1 and 66.2; 133Xe: 3.6 X 102 and 82.3; 140Ba: 2.3 X 10-2 and 59.4; 141Ce - 143Ce: 1.8 X 10-2 and 60.0. The fission product diffusion behavior, in general, fit either the vacancy or the substitutional-interstitial diffusion mechanisms for impurity atoms in a fcc metal. Both valence and ionic radius correlations were found. The data indicate low rates of diffusion for the operating temperatures at which α-thorium-based fuel might be used. (Auth.)
Primary Subject
Record Type
Journal Article
Journal
Journal of Nuclear Materials; v. 62(1); p. 17-25
Country of publication
ACTINIDES, BARIUM ISOTOPES, BETA DECAY RADIOISOTOPES, BETA-MINUS DECAY RADIOISOTOPES, BREEDER REACTORS, CERIUM ISOTOPES, CRYSTAL DEFECTS, CRYSTAL LATTICES, CRYSTAL STRUCTURE, CUBIC LATTICES, DAYS LIVING RADIOISOTOPES, ELEMENTS, ENERGY, ENERGY SOURCES, EPITHERMAL REACTORS, EVEN-EVEN NUCLEI, EVEN-ODD NUCLEI, FAST REACTORS, FBR TYPE REACTORS, FUELS, HEAT TREATMENTS, HOURS LIVING RADIOISOTOPES, INTERMEDIATE MASS NUCLEI, IODINE ISOTOPES, ISOMERIC TRANSITION ISOTOPES, ISOTOPES, LIQUID METAL COOLED REACTORS, METALS, MOLYBDENUM ISOTOPES, NUCLEAR FUELS, NUCLEI, ODD-EVEN NUCLEI, POINT DEFECTS, RADIOACTIVE MATERIALS, RADIOISOTOPES, RARE EARTH NUCLEI, REACTOR MATERIALS, REACTORS, TELLURIUM ISOTOPES, THORIUM, XENON ISOTOPES
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Fox, C.H. Jr.; Purcell, W.J.; Wieseneck, H.C.
Liquid metal engineering and technology. 3 v. Proceedings of the 3. international conference held in Oxford on 9-13 April 19841984
Liquid metal engineering and technology. 3 v. Proceedings of the 3. international conference held in Oxford on 9-13 April 19841984
AbstractAbstract
[en] This paper discusses recent experience in steam generator testing for the Clinch River Breeder Reactor Plant (CRBRP). The experience includes testing of a Prototype Steam Generator Module at the Energy Technology Engineering Center and iterative testing of flow models (including a full-scale flow model) to confirm the hydraulic design of the CRBRP Steam Generator Modules. The objectives of the testing are presented together with descriptions of the test articles and testing facilities, and the test results are discussed. (author)
Primary Subject
Source
British Nuclear Energy Society, London; International Atomic Energy Agency, Vienna (Austria). International Working Group on Fast Reactors; American Nuclear Society, La Grange Park, IL; European Nuclear Society, Petit-Lancy (Switzerland); 1516 p; ISBN 0 7277 0209 2; ; 1984; v. 2 p. 203-210; British Nuclear Energy Society; London (UK); 3. international conference on liquid metal engineering and technology; Oxford (UK); 9-13 Apr 1984; Price Pound150.00
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Book
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Conference
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