Hydrogen combustion in the containment building may be a threat to containment integrity. Especially in some subcompartments, local hydrogen detonation likely to happen, which may destroy the containment structure or the safety equipments in the containment. A study has been carried out using the GASFLOW three-dimensional CFD code to evaluate the hydrogen distribution in the subcompartment during a severe accident. The GASFLOW calculation has provided detailed results for the spatial distribution of gas concentrations in the reactor coolant pump (RCP) compartment and the steam generator (SG) compartment within containment, the high local hydrogen concentration was found in the local area. Then, three kinds of different hydrogen mitigation measures which were optimizing compartment structure, hydrogen recombiner and igniter were analyzed and compared. The σ criterion and λ criterion are used for conservative estimates of the flame acceleration (FA) potential and the possibility of deflagration to detonation transition (DDT) in the compartment after using the mitigation measures, respectively.
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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
CFD Analysis on Hydrogen Risk in Subcompartment of the Containment
Zhiqiang Zou,
Zhiqiang Zou
Nuclear Power Institute of China, Chengdu, Sichuan, China
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Jian Deng,
Jian Deng
Nuclear Power Institute of China, Chengdu, Sichuan, China
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Yu Zhang
Yu Zhang
Nuclear Power Institute of China, Chengdu, Sichuan, China
Search for other works by this author on:
Zhiqiang Zou
Nuclear Power Institute of China, Chengdu, Sichuan, China
Jian Deng
Nuclear Power Institute of China, Chengdu, Sichuan, China
Yu Zhang
Nuclear Power Institute of China, Chengdu, Sichuan, China
Paper No:
ICONE21-16171, V003T06A038; 7 pages
Published Online:
February 7, 2014
Citation
Zou, Z, Deng, J, & Zhang, Y. "CFD Analysis on Hydrogen Risk in Subcompartment of the Containment." 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. V003T06A038. ASME. https://doi.org/10.1115/ICONE21-16171
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