An experimental research on performance characteristics of passive residual heat removal system (PRHRS) for the small modular reactor designed by Nuclear Power Institute of China (NPIC) under the station blackout accident was performed in the CREAS facility, which consists of the primary system, the secondary system, the passive safety injection system, the passive residual heat removal system, the overpressure protection system and the auxiliary system. The experimental results show that, after the station blackout accident, a stable two-phase natural circulation between the steam generators and the heat exchanger in the PRHRS was established with a mass flow of 0.4T/h, thus the heat from the primary system was removed to the water in the containment water tank (CWT). During this period, the core decay residual heat and the sensible heat were removed from the primary system by the PRHRS effectively. The cold water from the core makeup tanks was injected into the reactor pressure vessel for core cooling. The peaked primary pressure was 16.3MPa and less than relief valve opening pressure 16.9MPa. In addition, the average coolant temperature of the reactor core reduced below 483 K, and the reactor operated safely.
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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:
978-0-7918-5003-9
PROCEEDINGS PAPER
Experimental Research on Characteristics of Passive Residual Heat Removal System for Small Modular Reactors Under the Station Blackout Accident Available to Purchase
Xiaodong Lu,
Xiaodong Lu
Nuclear Power Institute of China, Chengdu, China
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Chuanxin Peng,
Chuanxin Peng
Nuclear Power Institute of China, Chengdu, China
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Yan Zhang,
Yan Zhang
Nuclear Power Institute of China, Chengdu, China
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Xuesong Bai,
Xuesong Bai
Nuclear Power Institute of China, Chengdu, China
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Yuanfeng Zan,
Yuanfeng Zan
Nuclear Power Institute of China, Chengdu, China
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Wenbin Zhuo,
Wenbin Zhuo
Nuclear Power Institute of China, Chengdu, China
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Xiao Yan
Xiao Yan
Nuclear Power Institute of China, Chengdu, China
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Xiaodong Lu
Nuclear Power Institute of China, Chengdu, China
Chuanxin Peng
Nuclear Power Institute of China, Chengdu, China
Yan Zhang
Nuclear Power Institute of China, Chengdu, China
Xuesong Bai
Nuclear Power Institute of China, Chengdu, China
Yuanfeng Zan
Nuclear Power Institute of China, Chengdu, China
Wenbin Zhuo
Nuclear Power Institute of China, Chengdu, China
Xiao Yan
Nuclear Power Institute of China, Chengdu, China
Paper No:
ICONE24-60527, V003T09A036; 6 pages
Published Online:
October 25, 2016
Citation
Lu, X, Peng, C, Zhang, Y, Bai, X, Zan, Y, Zhuo, W, & Yan, X. "Experimental Research on Characteristics of Passive Residual Heat Removal System for Small Modular Reactors Under the Station Blackout Accident." Proceedings of the 2016 24th International Conference on Nuclear Engineering. Volume 3: Thermal-Hydraulics. Charlotte, North Carolina, USA. June 26–30, 2016. V003T09A036. ASME. https://doi.org/10.1115/ICONE24-60527
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