Lumped parameter method application in nuclear engineering – AP1000 DVI line break accident analysis by RELAP5

Article type: Research Article

Authors: Qiao, Xue-Dong | Jing, Jian-Ping^{; *} | An, Jie-Ru | Sun, Wei | Jia, Bin | Li, Yuan-Shan | Bi, Jin-Sheng | Zhuang, Shao-Xin | Zhang, Chun-Ming

Affiliations: Nuclear and Radiation Safety Center, Beijing, China

Correspondence: [*] Corresponding author: Jianping Jing, Nuclear and Radiation Safety Center, Beijing, China. Tel./Fax: +86 0188842625/0188840001; E-mail: jingjianping@chinansc.cn.

Abstract: Based on the PWR best estimate program RELAP5/MOD3.3, the reactor coolant system and the passive core cooling system of AP1000 Nuclear Power Plant were modeled and analyzed. Some key transient parameters were obtained, including RCS pressure, break discharge, etc. The result is in close agreement with the result generated by NOTRUMP code from Westinghouse (USA). The calculation results show that safeguard system of APl000 can effectively reduce the pressure of the first loop, also can prevent core uncovered. The safety of AP1000 during a small break Loss of Coolant Accident caused by DVI line breaking is verified.

Keywords: APl000, passive safety, direct vessel injection, small break loss of coolant accident

DOI: 10.3233/JCM-150519

Journal: Journal of Computational Methods in Sciences and Engineering, vol. 15, no. 1, pp. 63-71, 2015