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Conference Article: Afterheat removal for HTR-10 test module under accident conditions

Gao Zuying; He Shuyan; Zhang Min (Qinghua Univ., Beijing, BJ (China). Inst. of Nuclear Energy Technology)

Abstract

The reliable afterheat removal is a very important aspect for the reactor safety. In the preliminary design of HTR-10TM, a reactor cavity cooling system (RCCS) is arranged in the concrete reactor cavity with completely passive heat transfer. Two types of RCCS i.e. water RCCS and air RCCS are considered. The simple and reliable passive RCCS improves the safety and economy of the HTR-10TM. In this paper, a brief description of the RCCS design in HTR-10TM is presented. The heat removal characteristics of both water RCCS and air RCCS under the heatup test and accidents are described. They are analyzed by the THERMIX code.

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key words: Gas Cooled Reactor, Nuclear Technology
Reference:
Specialists meeting on decay heat removal and heat transfer under normal and accident conditions in gas cooled reactors. Juelich (Germany). 6-8 Jul 1992
International Atomic Energy Agency, Vienna (Austria)
IAEA-TECDOC--757, pp:63-72