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Conference Article: The Full Perfornance Test For The Safety Valves of HTR-10

Xinxin Wu, Jianling Dong, Rizhu Li, Institute of Nuclear and New Energy Technology, Beijing, CHINA

Abstract

Two sets of nuclear class I helium safety valves and nuclear class II steam pressure safety are installed, respectively, in the pressure relief systems of the primary loop and the over-pressure protection system of the second loop of 10MW High Temperature Helium Cooled Test Reactor HTR-10. They are ones of the key devices to guarantee the safety of HTR-10. The present paper gives the design requirements and structural peculiarity as well as performance requirements of the pressure relief valves. The demonstration tests for full performance of the safety valves were carried out in special test loop according to the requirements of ASME Section III codes. The test results showed that the performance of the safety valves can meet the design requirements and relevant nuclear codes.

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key words: high temperature gas cold reactor; nuclear class valve; valve design; test
Reference:
Proceedings of the Conference on High Temperature Reactors, Beijing, China, September, 22-24, 2004
International Atomic Energy Agency, Vienna (Austria)
HTR-2004, pp:1-10