Published 1993 | Version v1
Book

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

Part of:
2nd ASME-JSME international conference on nuclear engineering -- 1993

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).

Optional Information

Secondary number(s)
CONF-930352--.