Calculations for AP1000 nuclear power plant SGTR accident based on RELAP5/mod 3.3 program

Article type: Research Article

Authors: Jia, Bin | Jing, Jianping^{; *} | Qiao, Xuedong | Zhang, Chunming

Affiliations: Nuclear and Radiation Safety Center, Beijing, China

Correspondence: [*] Corresponding author: Jianping Jing, Nuclear and Radiation Safety Center, Beijing 100082, China. E-mail: [email protected].

Abstract: AP1000 nuclear power plant model is founded via RELAP5/mod 3.3 program in detail. Refer to SGTR accident basic assumptions in the safety analysis report, calculations for AP1000 nuclear power plant SGTR accident are carried out. And through comparison between the result got and the result from safety analysis report calculated by LOFTTR2 program, the two results are very consistent. It's found that even if the operators do not interfere, AP1000 nuclear power plant protection systems and passive design measures will trigger an automatic response measures, it can terminate the SG heat transfer tube leaking and make RCS be stable in a safe condition and to prevent SG overflowing and ADS actions occurring.

Keywords: RELAP5, AP1000, SGTR, SNAP

DOI: 10.3233/JCM-150522

Journal: Journal of Computational Methods in Sciences and Engineering, vol. 15, no. 1, pp. 81-90, 2015