Published October 2020 | Version v1
Journal article

Mass release and overfill analysis of SGTR accident for domestic advanced PWR

  • 1. Nuclear and Radiation Safety Center, State Environmental Protection Key Laboratory of Nuclear and Radiation Safety Regulatory Simulation and Validation, Beijing (China)

Description

In this paper Domestic Advanced PWR model is established using RELAP5/mod 3.3 code in detail. According to analysis assumptions in safety analysis report, research of SGTR accident for Domestic Advanced PWR is carried out. The max mass release of the accident and damaged SG max water volume are taken into account in the research for calculations respectively. During the research our main focus is on the characteristics of Domestic Advanced PWR SGTR accident and operation performance of vapor discharge appliance (VDA). Through the analysis of the calculation results of the two situations, it finds that although Domestic Advanced PWR has no high pressure safety injection system, however the rapid cooling and depressurization of the coolant system can be achieved through the operation of VDA, and then the medium pressure safety injection system invests as soon as possible. Later through the rational intervention of the operator, the ruptured SG heat transfer tube leaking can be terminated and the unit will be brought into a safe and stable state of operation. Finally the radioactivity consequence caused by the accident is within the acceptable dose level limit and the overflowing of the ruptured SG will never happen. (authors)

Additional details

Publishing Information

Journal Title
Chinese Journal of Nuclear Science and Engineering
Journal Volume
40
Journal Issue
5
Journal Page Range
p. 836-843
ISSN
0258-0918

Optional Information

Notes
3 figs., 4 tabs., 10 refs.