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Issues Associated With the Development of Severe Accident Management Guidelines for NPPs in China

[+] Author Affiliations
Zhiyi Yang, Yimin Chong, Chun Li, Xianhong Xu, Guohan Chai

Nuclear and Radiation Safety Center, Beijing, China

Jian Deng

Nuclear Power Institute of China, Chengdu, China

Paper No. ICONE21-16838, pp. V006T15A025; 5 pages
  • 2013 21st International Conference on Nuclear Engineering
  • Volume 6: Beyond Design Basis Events; Student Paper Competition
  • Chengdu, China, July 29–August 2, 2013
  • Conference Sponsors: Nuclear Engineering Division
  • ISBN: 978-0-7918-5583-6
  • Copyright © 2013 by ASME


After Fukushima nuclear accident, the Severe Accident Management Guidelines (SAMGs) are required according to the policy of the regulatory body in China. Most nuclear power plants (NPPs) in China adopt the technical approach of generic-SAMG of the Westinghouse Owner Group, consisting of severe accident control room guideline (SACRG), diagnostic flow chart (DFC), severe accident guideline (SAG), severe challenge status tree (SCST), severe challenge guideline (SCG), technical support center (TSC) long term monitoring guideline, and SAMG termination guideline (SAEG). A number of issues have been identified during the development of the SAMGs for M310+ NPPs, which is a dominant reactor type in China. The paper discussed these issues and identified some considerations for their resolution.

Copyright © 2013 by ASME



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