The In-containment Refueling Water Storage Tank (IRWST) provides low-pressure safety injection flow for passive CAP1400 Nuclear Power Plant (NPP) during Loss-Of-Coolant-Accident (LOCA) and subsequent Long Term Core Cooling (LTCC). The Passive Residual Heat Removal Heat Exchanger (PRHR HX) and the spargers of Automatic Depressurization System (ADS) stage 1∼3 are submerged in the IRWST. During small break LOCA, heat and mass are delivered through PRHR HX and ADS spargers to IRWST, and IRWST is heated up before its safety injection. However, numerical and experimental investigation has shown that IRWST is not perfect mixing, and thermal stratification exists. During ADS-4/IRWST initiation phase, the temperature of IRWST injection flow is of great importance, and is affected greatly by IRWST simulation method when modeling with system code like RELAP5. In this paper, two different IRWST simulation methods where one use multi channels in horizontal direction while the other use only one, are analyzed for CAP1400 SBLOCA with RE-LAP5, and their effects are compared. Finally, the better method which uses only one channel in horizontal direction is recommended.
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2017 25th International Conference on Nuclear Engineering
July 2–6, 2017
Shanghai, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5784-7
PROCEEDINGS PAPER
The Effect of IRWST Simulation Method on the Analysis of Small Break LOCA Using RELAP5
Caihong Xu,
Caihong Xu
Shanghai Nuclear Engineering Research & Design Institute, Shanghai, China
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Guobao Shi,
Guobao Shi
Shanghai Nuclear Engineering Research & Design Institute, Shanghai, China
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Kemei Cao,
Kemei Cao
Shanghai Nuclear Engineering Research & Design Institute, Shanghai, China
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Xiaoyu Cai,
Xiaoyu Cai
Shanghai Nuclear Engineering Research & Design Institute, Shanghai, China
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Zhanfei Qi
Zhanfei Qi
Shanghai Nuclear Engineering Research & Design Institute, Shanghai, China
Search for other works by this author on:
Caihong Xu
Shanghai Nuclear Engineering Research & Design Institute, Shanghai, China
Guobao Shi
Shanghai Nuclear Engineering Research & Design Institute, Shanghai, China
Kemei Cao
Shanghai Nuclear Engineering Research & Design Institute, Shanghai, China
Xiaoyu Cai
Shanghai Nuclear Engineering Research & Design Institute, Shanghai, China
Zhanfei Qi
Shanghai Nuclear Engineering Research & Design Institute, Shanghai, China
Paper No:
ICONE25-66219, V006T08A012; 7 pages
Published Online:
October 17, 2017
Citation
Xu, C, Shi, G, Cao, K, Cai, X, & Qi, Z. "The Effect of IRWST Simulation Method on the Analysis of Small Break LOCA Using RELAP5." Proceedings of the 2017 25th International Conference on Nuclear Engineering. Volume 6: Thermal-Hydraulics. Shanghai, China. July 2–6, 2017. V006T08A012. ASME. https://doi.org/10.1115/ICONE25-66219
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