Evaluation of ECCS performance for an SBWR
Description
A simplified boiling water reactor (SBWR), one of the next generation of light water reactors, is now under development. From the safety viewpoint, the SBWR is characterized by the adoption of a passive emergency core cooling system (ECCS) and a passive containment cooling system (PCCS). The ECCS network for an SBWR consists of depressurization valves (DPVs) and a gravity-driven cooling system (GDCS). The DPV and GDCS are designed to keep the core covered with water following any loss-of-coolant accident (LOCA) assuming a single failure in the ECCS. The SAPPHIRE code has been developed in order to evaluate the effectiveness of the ECCS of the SBWR. The SAPPHIRE code has been developed to calculate the short-term thermal-hydraulic phenomena simultaneously inside the contaminant including the RPV, drywell, and wetwell. The predictive capability of SAPPHIRE for SBWR LOCA analysis has been demonstrated by a comparison with the best estimate TRAC code. Both SAPPHIRE and TRAC codes indicate no core uncovery during a maximum drain line break
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 62
- Series
- Trans. Am. Nucl. Soc.
- Journal Page Range
- 665
- ISSN
- 0003-018X
- CODEN
- TANSA
Conference
- Title
- American Nuclear Society (ANS) winter meeting.
- Dates
- 11-15 Nov 1990.
- Place
- Washington, DC (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 22060636
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; COMPUTER CODES; COMPUTERIZED SIMULATION; CONTAINMENT SYSTEMS; DEPRESSURIZATION; DRAINAGE; ECCS; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; PASSIVITY; PERFORMANCE; PRESSURE VESSELS; REACTOR ACCIDENTS; REACTOR CORES; REACTOR SAFETY; S CODES; SPECIFICATIONS; T CODES
- Descriptors DEC
- ACCIDENTS; CONTAINERS; CONTAINMENT; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR COMPONENTS; REACTOR PROTECTION SYSTEMS; REACTORS; SAFETY; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-901101--.