Post-Irradiation Examination of Appr Fuel Element Irradiation Program Specimens PDF Download
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Languages : en
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APPR-type dispersion fuel element specimens containing temperature to respective burnups of approximately 50, 20, and 20% of uranium with no evidence of gross dimensional changes or loss of structural integrity. Blistering and/or core cracking has occurred when sections of 17.9 wt.% UO/sub 2/ specimens irradiated to burnups over 40% of uranium were subjected to post-irradiation annealing at 600 deg F for 24 hours. Post-irradiation core hardness measurements indicate that significant differences in irradiation damage exist between the various specimen types. These data indicate that the effects of the fabrication variables investigated in this program are as follows: The severity of irradiation damage in dispersion type fuel elements is inversely proportional to the UO/sub 2/ particle size of the fabricated plate. The particle size of the UO/ sub 2/ powder used in preparation of the initial core compact and the method of preparation of the UO/sub 2/ powders largely determine the final UO/sub 2/ particle size of roll-bonded, dispersion fuel plates. The particle size of the stainless steel powder used in the initial core mixture and the degree of cold reduction during final sizing of the fuel plate are apparently of relatively minor importance, at least for the systems investigated in this program. The severity of irradiation damage is directly proportional to the fuel concentration. Where an increased fuel loading is accompanied by an increase in the loading of the B/sub 4/C burnable poison to facilitate reactor control, the possibility of serious irradiation effects is increased to an even greater degree. (auth).
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Languages : en
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Book Description
APPR-type dispersion fuel element specimens containing temperature to respective burnups of approximately 50, 20, and 20% of uranium with no evidence of gross dimensional changes or loss of structural integrity. Blistering and/or core cracking has occurred when sections of 17.9 wt.% UO/sub 2/ specimens irradiated to burnups over 40% of uranium were subjected to post-irradiation annealing at 600 deg F for 24 hours. Post-irradiation core hardness measurements indicate that significant differences in irradiation damage exist between the various specimen types. These data indicate that the effects of the fabrication variables investigated in this program are as follows: The severity of irradiation damage in dispersion type fuel elements is inversely proportional to the UO/sub 2/ particle size of the fabricated plate. The particle size of the UO/ sub 2/ powder used in preparation of the initial core compact and the method of preparation of the UO/sub 2/ powders largely determine the final UO/sub 2/ particle size of roll-bonded, dispersion fuel plates. The particle size of the stainless steel powder used in the initial core mixture and the degree of cold reduction during final sizing of the fuel plate are apparently of relatively minor importance, at least for the systems investigated in this program. The severity of irradiation damage is directly proportional to the fuel concentration. Where an increased fuel loading is accompanied by an increase in the loading of the B/sub 4/C burnable poison to facilitate reactor control, the possibility of serious irradiation effects is increased to an even greater degree. (auth).
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Languages : en
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The Thermionic Fuel Element (TFE) Verification Program is funded by the Department of Energy (DOE) with the objective of demonstrating a fuel element design for a multimegawatt-class thermionic reactor for space power systems (Bohl and Ranken 1987). A number of contractors and DOE laboratories are involved in this program. These include General Atomics (GA), which is responsible for the overall technical development, fabrication, and processing of components and TFE prototypes for fast reactor testing and Westinghouse Hanford Company (WHC), which has the responsibility for implementation of the fast reactor irradiation program. 1 ref., 3 figs.
Author: IAEA
Publisher: International Atomic Energy Agency
ISBN: 920102021X
Category : Technology & Engineering
Languages : en
Pages : 149
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Post-irradiation examination (PIE) is an indispensable step in the selection of new or improved research reactor fuel, and in the characterization and understanding of its in-core behaviour. This publication provides an introduction to PIE techniques. It describes a typical PIE process from intercycle inspections in the reactor pool or channel, to hot cell PIE, which is subdivided into non-destructive and destructive testing techniques with their typical output, advantages and drawbacks, and their applicability to understanding fuel irradiation behaviour. Much of the work presented in this publication originated from the research and development of new low enriched uranium research reactor fuels. Intended readers include research reactor operators, regulators and their technical support organizations, fuel developers and manufacturers, laboratory staff, and policy makers.
Author:
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ISBN:
Category :
Languages : en
Pages : 119
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A program was carried out to determine the irradiation behavior of a PuO2-UO2 fast reactor fuel prototype. Forty stainless steel clad fuel specimens were fabricated, encapsulated, and irradiated in the General Electric Test Reactor to burnups ranging from 5000 to 99,000 MWD/T, and at heat fluxes ranging from 0.5 x 106 to 1.6 x 106 Btu/ hr-ft2. The cladding surface temperature ranged from 700 to 1200 deg F with most specimens in the 1000 to 1200 deg F range. All specimens were irradiated without rapture despite the high performance conditions imposed. Following irradiation, the fuel specimens were examined in the Radioactive Materials Laboratory. The post-irradiation examination consisted of dimensional measurements, gamma scans, determination of fission gas release, visual examination of the fuel, measurement of central voids, and metallographic examination of selected samples. Specimen and capsule fabrication is discussed, and the results of the postirradiation examination are presented and discussed.
Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 934
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Author: Arthur S. Mehner
Publisher:
ISBN:
Category : Nuclear fuel claddings
Languages : en
Pages : 266
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Author: J. M. Gerhart
Publisher:
ISBN:
Category : Nuclear fuels
Languages : en
Pages : 124
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Author: J. R. Weir
Publisher:
ISBN:
Category : Nuclear fuel elements
Languages : en
Pages : 44
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Author:
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ISBN:
Category :
Languages : en
Pages : 14
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Two chemically nickel-plated, internally and externally cooled, Hanford production fuel elements, which were irradiated to approximately 800 MWD/T as part of PT-IP-263-A, were transferred to the Radiometallurgy Laboratory in December 1960. The elements were selected for detailed examination because one had incurred a hot spot during irradiation and the other contained some unusual cracks in the nickel plate. Prior to irradiation, both fuel elements had been baked at 300 C to heat-treat the nickel plate. Also, the nickel plate of several unirradiated elements was damaged by scraping, marring, scratching and punching. The elements were exposed for six weeks to 105 C basin water, which was approximately the length of time the irradiated elements were in 105 C basin prior to transfer. Two unirradiated elements were submitted for comparison with irradiated pieces. The examination was requested by Process Engineering, Fuels Preparation Department; and Process and Reactor Development, Irradiation Processing Department, to determine the effects of irradiation on elements with improved nickel plating and to aid in evaluating the nickel-plated fuel element program.
Author: R. J. Sullivan
Publisher:
ISBN:
Category : Nuclear fuel elements
Languages : en
Pages : 42
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