Siting evaluation of High Temperature Engineering Test Reactor
- 1. Japan Atomic Energy Research Inst., Ibaraki (Japan)
- 2. Fuji Electric Co. Ltd., Tokyo (Japan). Nuclear Power Div.
Description
It is necessary to evaluate hypothetical accident to judge the appropriateness of reactor siting condition. Hypothetical accident is postulated assuming the occurrence of an accident which is unlikely to occur from a technical standpoint. The safety characteristics and/or advantages of the HTGRs are (1) slow response to core heatup events and (2) high temperature that fuel can sustain before the initiation of fission product release. A double-ended rupture of coaxial double pipe of the primary cooling system was selected as the hypothetical accident of the HTTR. Since the HTTR is a HTGR, the core temperature changes slowly and no instantaneous failure of coated fuel particles occur. Therefore, time-dependent release model was newly introduced to calculate the release amount of core contained fission products during the accident. From the result based on the analytical model developed here, appropriateness of siting condition of the HTTR was confirmed
Additional details
Publishing Information
- Publisher
- American Society of Mechanical Engineers.
- Imprint Place
- New York, NY (United States)
- ISBN
- 0-7918-0636-7
- Imprint Title
- 2nd ASME-JSME international conference on nuclear engineering -- 1993
- Imprint Pagination
- 770 p.
- Journal Page Range
- p. 573-580.
Conference
- Title
- 2. Japan Society of Mechanical Engineers (JSME)/American Society of Mechanical Engineers (ASME) joint international conference on nuclear engineering.
- Dates
- 21-24 Mar 1993.
- Place
- San Francisco, CA (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 25058071
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DESIGN; FISSION PRODUCT RELEASE; HTTR REACTOR; RADIATION DOSES; REACTOR ACCIDENTS; REACTOR SAFETY; SITE SELECTION; SOURCE TERMS
- Descriptors DEC
- ACCIDENTS; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; REACTORS; RESEARCH AND TEST REACTORS; SAFETY
Optional Information
- Secondary number(s)
- CONF-930352--.