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Sawa, Kazuhiro; Okamoto, Futoshi; Shiozawa, Shusaku; Sasaki, Katsunori.
Japan Atomic Energy Research Inst., Tokyo (Japan)1990
Japan Atomic Energy Research Inst., Tokyo (Japan)1990
AbstractAbstract
[en] This report describes an analytical model and parameters to evaluate the fractional release of metallic fission product (cesium) during normal operation of High Temperature Engineering Test Reactor (HTTR). The fractional releases, which are calculated by TRAFIC code, on the basis of the present analytical model and parameters show about ten times larger than that measured in the sweep gas capsule irradiation test and the OGL-1 fuel element irradiation test. Thus, the analytical model and the parameters are concluded to be applicable to the evaluation of the cesium release from the HTTR fuel element in the safety analysis. (author)
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Mar 1990; 46 p
Record Type
Report
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BETA DECAY RADIOISOTOPES, BETA-MINUS DECAY RADIOISOTOPES, CESIUM ISOTOPES, COMPUTER CODES, COOLING SYSTEMS, ENRICHED URANIUM REACTORS, EXPERIMENTAL REACTORS, FUEL PARTICLES, GAS COOLED REACTORS, GRAPHITE MODERATED REACTORS, HELIUM COOLED REACTORS, HTGR TYPE REACTORS, INTERMEDIATE MASS NUCLEI, ISOTOPES, NUCLEI, ODD-EVEN NUCLEI, RADIOISOTOPES, REACTOR COMPONENTS, REACTOR COOLING SYSTEMS, REACTORS, RESEARCH AND TEST REACTORS, YEARS LIVING RADIOISOTOPES
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