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
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 55067963
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CHINA; COOLING SYSTEMS; DEPRESSURIZATION; HEAT TRANSFER; LEAKS; MASS; PWR TYPE REACTORS; RADIOACTIVITY; SAFETY INJECTION; STEAM GENERATOR TUBE RUPTURE; TUBES; WATER
- Descriptors DEC
- ACCIDENTS; ASIA; ENERGY SYSTEMS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; HYDROGEN COMPOUNDS; OXYGEN COMPOUNDS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 3 figs., 4 tabs., 10 refs.