This paper describes the analysis of main steam line break at hot shutdown state performed using a new developed method where a 3D core neutronics code, a core thermal-hydraulics code and a plant simulation computer code are fully coupled. Models, main hypothesis applied and calculation results of the main steam line break (MSLB) accident analysis are presented. To cover as many as states points a new parameter named Transient Reactivity Variation (TRV) is introduced, the conservatism of this parameter when doing safety analysis are evaluated also. The study shows that the coupled method using some best estimate parameters can get more margins compared with the traditional analysis method, and the TRV can be used as a key parameter to determine which core configuration is the most penalizing case.
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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
Analysis of Main Steam Line Break Accident at Hot Shutdown State Using a Coupled Method
Dawei Cui,
Dawei Cui
China Nuclear Power Technology Research Institute, Shenzhen, Guangdong, China
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Jinzhen Leng,
Jinzhen Leng
China Nuclear Power Technology Research Institute, Shenzhen, Guangdong, China
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Jun Chen
Jun Chen
China Nuclear Power Technology Research Institute, Shenzhen, Guangdong, China
Search for other works by this author on:
Dawei Cui
China Nuclear Power Technology Research Institute, Shenzhen, Guangdong, China
Jinzhen Leng
China Nuclear Power Technology Research Institute, Shenzhen, Guangdong, China
Jun Chen
China Nuclear Power Technology Research Institute, Shenzhen, Guangdong, China
Paper No:
ICONE21-15007, V003T10A001; 6 pages
Published Online:
February 7, 2014
Citation
Cui, D, Leng, J, & Chen, J. "Analysis of Main Steam Line Break Accident at Hot Shutdown State Using a Coupled Method." 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. V003T10A001. ASME. https://doi.org/10.1115/ICONE21-15007
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