A study of RCS depressurization strategy of CPR1000 SAMG
Author:
Yu Peizhao12, Zheng Jianxiang12, Li Jun12, Miao Huifang12, Wu Ling12, Gu Danying3
Affiliation:
1. College of Energy , Xiamen University , No. 4221-104 Xiangan South Road , Xiamen 361002, P. R. China 2. Fujian Research Center for Nuclear Engineering , Xiamen City , Fujian Province , 361102 , P. R. China 3. Shanghai Nuclear Engineering Research & Design Institute Co. Ltd , No. 29 Hong Cao Road , Shanghai 200233, P. R. China
Abstract
Abstract
CPR1000 severe accident management guideline (SAMG) is a product of the Westinghouse Owners Group (WOG) SAMG and the French SAMG (called GIAG) combination. It adopts the structure of WOG SAMG. However, it follows the approach of GIAG performing reactor coolant system (RCS) depressurization immediately after entering SAMG. This is a special feature of CPR1000 SAMG. The purpose of this paper is to evaluate this RCS depressurization strategy. The simulations of a station blackout (SBO) accident are performed for CPR1000 with RCS depressurization strategy adopted at both core exit temperature (CET) of 650 and 1100 °C together with opening different number of safety relief valves (SRV) using an integral severe accident analysis code. The optimized RCS depressurization strategy is provided to delay the reactor pressure vessel (RPV) failure time. And some comments are provided for future improvement.
Funder
National Natural Science Funds of China Natural Science Foundation of Fujian Province of China
Publisher
Walter de Gruyter GmbH
Subject
Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics,Radiation
Reference11 articles.
1. Henry, C.E. and Landgren, V. (2003). MAAP4 modular accident analysis program for LWR power plants, computer code user’s manual. Electric Power Research Institute, Palo Alto. 2. Jacquemain, D., Cenerino, G., Corenwinder, F., Raimond, E.I., Bentaib, A., Bonneville, H., Clement, B., Cranga, M., Fichot, F., and Koundy, V. (2015). Nuclear power reactor core melt accidents. Current state of knowledge. EDP Sciences, France. 3. Nelder, J.A. and Mead, R. (1965). A simplex method for function minimization. Comput. J. 7: 308–313, https://doi.org/10.1093/comjnl/7.4.308. 4. Ni, X., Zheng, J., Hou, E., Hao, J., Bian, B., and Li, N. (2016). Simulation of early phase radioactivity of CPR1000 plant under LOCAs based on RELAP5-3D core engineering simulator. Prog. Nucl. Energy 93: 47–58, https://doi.org/10.1016/j.pnucene.2016.07.019. 5. Wang, S.-J., Chiang, K.-S., and Chiang, S.-C. (2004). Analysis of PWR RCS injection strategy during severe accident. Nucl. Technol. 146: 199–205, https://doi.org/10.13182/nt04-a3498.
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