The conservatism was introduced in the probabilistic safety analysis (PSA) while successes criteria for the event tree were determined. The conservatism has strong relation with the uncertainty but independent with the uncertainty, and the conservatism could significantly influence the CDF results, contribution of dominant sequence, and sensitivity analysis. For methodology, the conservatism in PSA was identified, conservative numbers were defined to quantify the conservatism. Addressing the loss of feed water (LOFW) accident at the PWR, the probability distributions for the function events of the event tree were defined, and the conservatism was quantified based on the PSA insights and sensitivity analysis. The methodology and the application of the conservative numbers were discussed and conclusions were drawn.
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2013 21st International Conference on Nuclear Engineering
July 29–August 2, 2013
Chengdu, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5580-5
PROCEEDINGS PAPER
PSA Conservatism Analysis and Quantification for the LOFW Accident Available to Purchase
Tony X. Kong,
Tony X. Kong
Science & Technology on Reactor System Design Technology Laboratory, Chengdu, China
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Chunrui Deng,
Chunrui Deng
Science & Technology on Reactor System Design Technology Laboratory, Chengdu, China
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Ivan Vrbanic,
Ivan Vrbanic
APOSS Consulting Company, Zabok, Croatia
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Ivica Basic
Ivica Basic
APOSS Consulting Company, Zabok, Croatia
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Tony X. Kong
Science & Technology on Reactor System Design Technology Laboratory, Chengdu, China
Chunrui Deng
Science & Technology on Reactor System Design Technology Laboratory, Chengdu, China
Ivan Vrbanic
APOSS Consulting Company, Zabok, Croatia
Ivica Basic
APOSS Consulting Company, Zabok, Croatia
Paper No:
ICONE21-15299, V003T06A011; 10 pages
Published Online:
February 7, 2014
Citation
Kong, TX, Deng, C, Vrbanic, I, & Basic, I. "PSA Conservatism Analysis and Quantification for the LOFW Accident." Proceedings of the 2013 21st International Conference on Nuclear Engineering. Volume 3: Nuclear Safety and Security; Codes, Standards, Licensing and Regulatory Issues; Computational Fluid Dynamics and Coupled Codes. Chengdu, China. July 29–August 2, 2013. V003T06A011. ASME. https://doi.org/10.1115/ICONE21-15299
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