CANDU6 ECC line break analysis
- 1. Korea Atomic Energy Research Institute (Korea, Republic of)
- 2. Atomic Energy of Canada Limited, Ontario (Canada)
Description
Detailed thermalhydraulic analysis for two 100% ECC line breaks in CANDU6 are performed to predict the response of the primary and secondary heat transport systems. Two break locations are selected: in the ECCS injection line connected to reactor inlet header and outlet header. The analysis is performed using the thermalhydraulic computer code, CATHENA. A limiting single channel analysis is also performed to give the maximum fuel temperature. As soon as the break occurs, the reactor power increases rapidly due to positive void reactivity. This increase during blowdown period is arrested by fast reactor trip. The late fuel heatup after reactor trip is observed in critical core pass due to low flow condition and delayed ECC injection. However, these heatup are lower than those of 35% RIH and 100% ROH break which were found as the worst case in terms of fuel heatup and fission product release. Therefore, it can be concluded that there is no need of performing the ECC line break analysis
Additional details
Publishing Information
- Imprint Title
- Proceedings of fifth international topical meeting on nuclear thermal hydraulics, operations and safety
- Imprint Pagination
- 1493 p.
- Journal Page Range
- p. I3.1-I3.6
Conference
- Title
- 5. international topical meeting on nuclear thermal hydraulics, operations and safety
- Dates
- 14-18 Apr 1997
- Place
- Beijing (China)
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 29048801
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- C CODES; CANDU TYPE REACTORS; COMPUTERIZED SIMULATION; ECCS; FLOW RATE; LOSS OF COOLANT; PRIMARY COOLANT CIRCUITS; RESPONSE FUNCTIONS; RUPTURES; SAFETY ANALYSIS; SECONDARY COOLANT CIRCUITS; STEADY-STATE CONDITIONS; TRANSIENTS; VOID FRACTION
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; COOLING SYSTEMS; ENGINEERED SAFETY SYSTEMS; FAILURES; FUNCTIONS; HEAVY WATER MODERATED REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTOR PROTECTION SYSTEMS; REACTORS; SIMULATION; THERMAL REACTORS