The method for ATWS (anticipated transient without scram) analysis was completely developed for commercial pressurized water (PWR) reactor plants, especially for selecting of typical initial events. For accident analysis of ATWS, it is different between PWR and small modular reactor (SMR), as different structures and characters, and it is necessary to study the typical initial events for these reactors. Based on the standard of PWR, the demanding for ATWS analysis was studied and the consequences for typical anticipated transient was calculated using RELAP5/MOD3.2 code, “maintain reactor coolant pressure boundary integrity” was selected as limiting criterion. The results shows for SMR, anticipated transient with the most serious consequence for ATWS are loss of offsite power and inadvertent control rod withdraw event, this conclusion will support to prepare the safety analysis report and optimum design of diversity activation system (DAS) for SMR.
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2016 24th International Conference on Nuclear Engineering
June 26–30, 2016
Charlotte, North Carolina, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5002-2
PROCEEDINGS PAPER
Study on Typical Initial Event of ATWS for Small Modular Reactor Available to Purchase
Zhang Dan,
Zhang Dan
Nuclear Power Institute of China, Chengdu, China
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Ran Xu,
Ran Xu
Nuclear Power Institute of China, Chengdu, China
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Qiu Zhifang,
Qiu Zhifang
Nuclear Power Institute of China, Chengdu, China
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Zhou Ke,
Zhou Ke
Nuclear Power Institute of China, Chengdu, China
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Feng Li
Feng Li
Nuclear Power Institute of China, Chengdu, China
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Zhang Dan
Nuclear Power Institute of China, Chengdu, China
Ran Xu
Nuclear Power Institute of China, Chengdu, China
Qiu Zhifang
Nuclear Power Institute of China, Chengdu, China
Zhou Ke
Nuclear Power Institute of China, Chengdu, China
Feng Li
Nuclear Power Institute of China, Chengdu, China
Paper No:
ICONE24-61166, V002T06A041; 6 pages
Published Online:
October 25, 2016
Citation
Dan, Z, Xu, R, Zhifang, Q, Ke, Z, & Li, F. "Study on Typical Initial Event of ATWS for Small Modular Reactor." Proceedings of the 2016 24th International Conference on Nuclear Engineering. Volume 2: Smart Grids, Grid Stability, and Offsite and Emergency Power; Advanced and Next Generation Reactors, Fusion Technology; Safety, Security, and Cyber Security; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues. Charlotte, North Carolina, USA. June 26–30, 2016. V002T06A041. ASME. https://doi.org/10.1115/ICONE24-61166
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