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Title: Advanced vessel cooling system concept for high-temperature gas-cooled reactors

Journal Article · · Nuclear Technology
OSTI ID:477295
; ;  [1]
  1. Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan)

The high-temperature gas-cooled reactor (HTGR) program will be attractive to a broad range of owner/operators and meet public acceptance if the future HTGRs would be completely free from accidents, which cause a significant release of radioactivity into the environment. An advanced vessel cooling system concept, in which there is no heat loss in normal operation and the decay heat is removed by the natural circulation of air in an accident, is proposed for the High-Temperature Engineering Test Reactor to this requirement. The depressurization accident, one of the severest accidents of the HTGR, is selected and the analysis shows no significant core heatup. Applicability to the future HTGR is also investigated.

OSTI ID:
477295
Journal Information:
Nuclear Technology, Vol. 118, Issue 2; Other Information: PBD: May 1997
Country of Publication:
United States
Language:
English