Large-break accident analysis of supercritical water-cooled reactor CSR1000
- 1. Science and Technology on Reactor System Design Technology, Nuclear Power Institute of China, Chengdu (China)
- 2. School of Nuclear Science and Technology, Xi'an Jiaotong University (China)
Description
Large-break accident analysis of China Super-critical water-cooled Reactor with the related electric power of 1000 MW (CSR1000) were carried out using APROS code to clarify its characteristics and to evaluate the capability of its safety system. At the cold-leg large-break, the reverse-flow in the core happens immediately due to the blowdown of coolant at the break. The reverse-flow drives the high temperature and low density fluid into the core, which results in the heat transfer deterioration in the core and the cladding temperature increasing quickly. After the opening of ADS valves, the positive-flow in the core has been covered, and the excessive core heat-up has been mitigated. The high feedwater tank can provide the coolant supply at the early period; therefore, the low pressure injection system gets more time to be actuated. After the blowdown phase, the core has been re-flooded gradually by low pressure safety injection system. The maximum cladding temperature of large break accident is lower than the criterion (1260℃) by about 340℃, which appears during the blowdown phase. (authors)
Additional details
Publishing Information
- Journal Title
- Nuclear Power Engineering
- Journal Volume
- 34
- Journal Issue
- 1
- Journal Page Range
- p. 78-82
- ISSN
- 0258-0926
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 47112211
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BLOWDOWN; CHINA; FEEDWATER; FUEL CANS; HEAT TRANSFER; LOSS OF COOLANT; LOW PRESSURE COOLANT INJECTION; REACTOR ACCIDENTS; SAFETY INJECTION; SUPERCRITICAL STATE; TEMPERATURE RANGE 0400-1000 K; VALVES; WATER COOLED REACTORS
- Descriptors DEC
- ACCIDENTS; ASIA; CONTROL EQUIPMENT; ECCS; ENERGY TRANSFER; ENGINEERED SAFETY SYSTEMS; EQUIPMENT; FLOW REGULATORS; HYDROGEN COMPOUNDS; OXYGEN COMPOUNDS; REACTOR ACCIDENTS; REACTOR PROTECTION SYSTEMS; REACTORS; TEMPERATURE RANGE; WATER
Optional Information
- Notes
- 8 figs., 3 tabs., 4 refs.