Nuclear Techniques ›› 2016, Vol. 39 ›› Issue (8): 80605-080605.doi: 10.11889/j.0253-3219.2016.hjs.39.080605

• NUCLEAR ENERGY SCIENCE AND ENGINEERING • Previous Articles    

Probabilistic safety assessment for SGTR in advanced passive nuclear power plant

PAN Yalan1,2, LUAN Xiuchun2, WANG Zhe1, ZUO Jiaxu1, SONG Wei1   

  1. 1 Nuclear and Radiation Safety Center, Beijing 100082, China;
    2 Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, Harbin Engineering University, Harbin 150001, China
  • Received:2016-04-10 Revised:2016-05-21 Online:2016-08-10 Published:2016-08-15
  • Supported by:

    Supported by National Science and Technology Major Project (No.2013ZX06002001-004)

Abstract:

Background: The Steam Generator Tube Rupture (SGTR) accident, which has its own characteristics, is one of the important accidents in nuclear power plants, and it is significant to the safety of the nuclear power station. Purpose: In this paper, AP1000 reactor is selected as the typical advanced passive nuclear power plant to analyze the core damage consequence caused by SGTR accident, so as to find out the weak links existing in the system. Methods: The Probabilistic Safety Assessment (PSA) method in level one has been used to analyze the SGTR accident in AP1000. After the power plant accident occurs, systems, equipment and personnel respond differently, event tree analysis method is used to obtain sequence, and the systems related to this accident are analyzed by fault tree models. Results: By the Risk Spectrum software, the total Core Damage Probability (CDF) has been calculated, and the minimal cut sets, the importance measures and the sensibility of the core damage have also been analyzed respectively. Conclusion: According to a series of analysis results, the most important basic events resulting in the core damage can be obtained, and the weak link of the system can be found, which has a certain theoretical support for the further strengthening of accident prevention and mitigation of the core damage caused by the accident.

Key words: Advanced passive nuclear power plants, SGTR, CDF, PSA

CLC Number: 

  • TL364+.5