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Conference Article: Analysis of stress in reactor core vessel under effect of pressure lose shock wave

L. Yong, L. Baoting (Institute of Nuclear Energy Technology Tsinghua University, Beijing)

Abstract

High Temperature gas cooled Reactor (HTR-10) is a modular High Temperature gas cooled Reactor of the new generation. In order to analyze the safety characteristics of its core vessel in case of large rupture accident, the transient performance of its core vessel under the effect of pressure lose shock wave is studied, and the transient pressure difference between the two sides of the core vessel and the transient stresses in the core vessel is presented in this paper, these results can be used in the safety analysis and safety design of the core vessel of HTR-10.

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key words: Gas Cooled Reactor, Nuclear Technology
Reference:
Proceedings of a Technical Committee Meeting held in Beijing, People's Republic of China, 2-4 November 1998
International Atomic Energy Agency, International Working Group on Gas-Cooled Reactors, Vienna (Austria)
IAEA-TECDOC--1210, pp:181-185