Probabilistic safety assessment (PSA) uses a systematic approach to estimate the reliability and risk of a nuclear power plant (NPP). Over the past few years, severe accident management guidance (SAMG), which delineates the mitigation actions of core melt accidents of an NPP, has been developed to support operators and staff in the technical support center in dealing with those misfortunes. It can be expected that the implementation of SAMG will reduce the amount of radionuclides released to the environment during the accident. The plant studied is a three-loop pressurized water reactor (PWR) with large dry containment. The RCS depressurization and reactor cavity flooding can be used as an accident management strategy. Then, the decrease of LERF (Large and Early Release Frequency) is quantified using PSA approach. It can be found that strategy of RCS depressurization and reactor cavity flooding can mitigate the result of severe accident effectively.
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18th International Conference on Nuclear Engineering
May 17–21, 2010
Xi’an, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4931-6
PROCEEDINGS PAPER
Assessment for Effect of RCS Depressurization and Reactor Cavity Flooding Using PSA Approach Available to Purchase
Changhong Peng,
Changhong Peng
China Nulcear Power Technology Research Institute, Shenzhen, China
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Ning Zhang,
Ning Zhang
China Nulcear Power Technology Research Institute, Shenzhen, China
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Pingping Liu
Pingping Liu
China Nuclear Power Technology Research Institute, Shenzhen, China
Search for other works by this author on:
Changhong Peng
China Nulcear Power Technology Research Institute, Shenzhen, China
Ning Zhang
China Nulcear Power Technology Research Institute, Shenzhen, China
Pingping Liu
China Nuclear Power Technology Research Institute, Shenzhen, China
Paper No:
ICONE18-29159, pp. 369-373; 5 pages
Published Online:
April 8, 2011
Citation
Peng, C, Zhang, N, & Liu, P. "Assessment for Effect of RCS Depressurization and Reactor Cavity Flooding Using PSA Approach." Proceedings of the 18th International Conference on Nuclear Engineering. 18th International Conference on Nuclear Engineering: Volume 3. Xi’an, China. May 17–21, 2010. pp. 369-373. ASME. https://doi.org/10.1115/ICONE18-29159
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