Research on capability of secondary passive residual decay heat removal system after Main Feedwater Line Break (MFLB) accident
- 1. Beijing Key Laboratory of Passive Safety Technology for Nuclear Energy, North China Electric Power University, Beijing (China)
- 2. School of Nuclear Science and Engineering, North China Electric Power University, Beijing (China)
- 3. China Nuclear Power Engineering Co., Ltd (China)
Description
Highlights: • PRS startup performance and decay heat removal capability after MFLB accident were investigated. • PRS startup response was investigated and strategy 3 is recommended due to minimum fluctuation during initiating stage. • MFLB was simulated with PRS availability. No overall boiling occurred in primary circuit. - Abstract: All advanced NPPs are required to improve safety strategy to cope with design extension condition (DEC) after Fukushima accident. One design improvements for HPR1000 is adoption of secondary Passive Residual Heat Removal System (PRS) to cope with station blackout accident together with loss of all feedwater, which can help to strengthen defense in depth capability and enrich DEC mitigation measures. To make the best use of PRS decay heat removal capability, investigation of PRS startup performance and decay heat removal capability after MFLB accident are investigated based on HPR1000 RELAP5 model. PRS startup response featured by pressure, mass flow rate and void fraction are investigated under three startup strategies. Strategy 3(backflow valve open strategy) is recommended due to minimum fluctuation during initiating stage, in which strategy steam isolation valve is normally open and backflow isolation valve is used to initiate PRS. Then Main Feedwater Line Break (MFLB) accident was simulated with the assumption of loss of auxiliary feedwater. Response characteristics in primary loop and PRS are investigated. After PRS being initiated after scram with 60 s delay, natural circulation in PRS will establish rapidly, and decay heat will be removed under natural circulation operation mode. No overall boiling occurred in primary circuit before isolation of affected SG. Secondary PRS is adequate to remove decay heat after DEC.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2017.10.013Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2017.10.013;
- PII
- S0029549317304922;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 325
- Journal Page Range
- p. 156-163
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 50082428
- Subject category
- S42: ENGINEERING;
- Descriptors DEI
- AFTER-HEAT REMOVAL; DECAY; FEEDWATER; FLOW RATE; FUKUSHIMA DAIICHI NUCLEAR POWER STATION; NATURAL CONVECTION; PRIMARY COOLANT CIRCUITS; RHR SYSTEMS; SIMULATION; STATION BLACKOUT; VALVES; VOID FRACTION
- Descriptors DEC
- ACCIDENTS; CONTROL EQUIPMENT; CONVECTION; COOLING SYSTEMS; ENERGY SYSTEMS; ENERGY TRANSFER; EQUIPMENT; FLOW REGULATORS; HEAT TRANSFER; HYDROGEN COMPOUNDS; MASS TRANSFER; OXYGEN COMPOUNDS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTOR SITES; REMOVAL; WATER
Optional Information
- Notes
- © 2017 Elsevier B.V. All rights reserved.