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AbstractAbstract
[en] The effect of flux-shape changes resulting from the replacement of the B-ring 8.5 w/o fuel with 12 w/o fuel has been studied with the aid of the diffusion code Exterminator-2. The effect of the higher w/o fuel is to slightly depress the B-ring flux, but to considerably increase the B-ring power density. The Fuchs-Nordheim model has been used to predict the B-ring temperature rises for both old and new B-ring configurations, and both are well under the 800 deg. C safety limit. Steady-state analysis of 1.0 MW operation indicates that the B-ring fuel-center temperature rises from 320 deg. C to 408 deg. C in the replacement. Analysis of both a B-ring fuel-element failure and a complete loss-of-coolant accident shows that neither should present an unacceptable fuel-heating problem. (author)
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Source
General Atomic Co., San Diego, CA (United States); Oregon State University Radiation Center, Corvallis, OR (United States); 204 p; 1978; p. 4.20-4.28; 6. TRIGA owners' conference; Corvallis, OR (United States); 26 Feb - 2 Mar 1978; Country of input: International Atomic Energy Agency (IAEA); Abstract on p. xiii; 5 refs, 3 figs
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
ACCIDENTS, ENERGY SOURCES, ENRICHED URANIUM REACTORS, FAILURES, FUELS, HOMOGENEOUS REACTORS, HYDRIDE MODERATED REACTORS, IRRADIATION REACTORS, ISOTOPE PRODUCTION REACTORS, MATERIALS, OPERATION, PULSED REACTORS, REACTOR ACCIDENTS, REACTOR MATERIALS, REACTORS, RESEARCH AND TEST REACTORS, SAFETY, SOLID HOMOGENEOUS REACTORS, THERMAL REACTORS, TRAINING REACTORS, TRIGA TYPE REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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