In this paper, operating characteristics of the safety system of Chinese Supercritical Water-cooled Reactor (CSR1000) is described. Selecting CSR1000 as the focus of research, and it’s active and passive safety systems are analyzed in turn. A comparison is given between these two types of safety systems. Henceforth, the features of the safety control systems of CSR1000 are obtained. The results show that for the active systems, the control speed of the pressure control system is the fastest and that of the power control system is the slowest. It is observed that the active control system exhibits simple harmonic oscillation. On the other hand, the control feature of passive control system is stable. In addition, coupling the safety systems can ensure the safety of CSR1000 in the event of a loss of flow accident (LOFA).
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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
Analysis on Safety System Operating Characteristic of SCWR
Liang Liu,
Liang Liu
North China Electric Power University, Beijing, China
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Tao Zhou,
Tao Zhou
North China Electric Power University, Beijing, China
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Jie Chen,
Jie Chen
North China Electric Power University, Beijing, China
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Ali Shahzad Muhammad,
Ali Shahzad Muhammad
North China Electric Power University, Beijing, China
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Juan Chen,
Juan Chen
North China Electric Power University, Beijing, China
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Bangyang Xia
Bangyang Xia
China Nuclear Power Institute Nuclear Reactor System Design Technology Laboratory, Chengdu, China
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Liang Liu
North China Electric Power University, Beijing, China
Tao Zhou
North China Electric Power University, Beijing, China
Jie Chen
North China Electric Power University, Beijing, China
Ali Shahzad Muhammad
North China Electric Power University, Beijing, China
Juan Chen
North China Electric Power University, Beijing, China
Bangyang Xia
China Nuclear Power Institute Nuclear Reactor System Design Technology Laboratory, Chengdu, China
Paper No:
ICONE24-60501, V002T07A009; 7 pages
Published Online:
October 25, 2016
Citation
Liu, L, Zhou, T, Chen, J, Muhammad, AS, Chen, J, & Xia, B. "Analysis on Safety System Operating Characteristic of SCWR." 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. V002T07A009. ASME. https://doi.org/10.1115/ICONE24-60501
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