Comparative analysis of auxiliary feedwater system and passive safety system under typical accident scenarios for integrated pressurized water reactor (IPWR)
- 1. State Key Laboratory of Multiphase Flow in Power Engineering, Department of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an, 710049 (China)
Description
The Integrated Pressurized Water Reactor (IPWR) designed with series of passive safety system has been regarded as a very promising reactor concept. In this paper, in order to assess the accident mitigation ability of passive safety systems in China 100 MW IPWR, the complete system models, including the reactor vessel, passive safety injection system and passive residual heat removal system, were established using RELAP5 software. The comprehensive and quantitative comparative analysis of auxiliary feed water system and passive safety system under typical accident scenarios, including loss of flow accident and Station Black-out (SBO), were investigated, respectively. Results show that the passive residual heat removal system has the similar accident mitigation capability compared with the auxiliary feed water system, which is adopted in most of traditional PWR design. And the IPWR could realize the reactor safe shutdown under typical accident scenarios with passive safety systems. Finally, the Small break loss of coolant accident (SBLOCA) induced by pressurizer surge line rupture was calculated to verify the function of passive safety systems for IPWR. Results demonstrate that the passive safety system could provide emergency coolant to the reactor and remove the reactor decay heat successfully. This work is meaningful for the quantitative evaluation of passive safety systems in IPWR.
Additional details
Identifiers
- DOI
- 10.1016/j.pnucene.2019.03.020;
- PII
- S014919701930085X;
Publishing Information
- Journal Title
- Progress in Nuclear Energy
- Journal Volume
- 115
- Journal Page Range
- p. 42-51
- ISSN
- 0149-1970
- CODEN
- PNENDE
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 55022550
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- AFTER-HEAT; AFTER-HEAT REMOVAL; COMPUTER CODES; COOLANTS; FEEDWATER; LOSS OF FLOW; PRESSURIZERS; PWR TYPE REACTORS; REACTOR DESIGN; REACTOR SHUTDOWN; REACTOR VESSELS; RHR SYSTEMS; SAFETY INJECTION; SBLOCA; STATION BLACKOUT
- Descriptors DEC
- ACCIDENTS; CONTAINERS; COOLING SYSTEMS; DESIGN; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; HYDROGEN COMPOUNDS; LOSS OF COOLANT; OXYGEN COMPOUNDS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTOR LIFE CYCLE; REACTORS; REMOVAL; SHUTDOWN; THERMAL REACTORS; WATER; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Copyright
- Copyright (c) 2019 Elsevier Ltd. All rights reserved.