ATWS mitigation for a BWR-2
Creators
- 1. GPU Nuclear Corp., 100 Interpace Parkway, Parsippany, NJ 07054
Description
One major concern during an isolation ATWS event from power operation is the need to reduce reactor power as early as possible in order to minimize suppression pool heatup via relief valve blowdown and thus increase the time available to shut the reactor down. A means of accomplishing this for a BWR-2 during ATWS conditions is to trip the recirculation pumps and initiate isolation condensers automatically on high system pressure and then intentionally allow the core power generation and system coolant inventory to reach equilibrium by manual termination of feedwater. The results using the RELAP5/MOD1 code for Main Steam Isolation Valve Closure and Loss of Feedwater ATWS events, show that core power is reduced to a value approximately equal to that of the emergency condenser steam relief capacity while core cooling is maintained and suppression pool heatup is minimized
Additional details
Publishing Information
- Publisher
- American Nuclear Society.
- Imprint Place
- La Grange Park, IL (USA)
- ISBN
- 0-89448-122-3
- Imprint Title
- Proceedings of third international topical meeting on reactor thermal hydraulics
- Journal Page Range
- p. 3.E1-3.E6.
Conference
- Title
- 3. international meeting on reactor thermal hydraulics.
- Dates
- 15-18 Oct 1985.
- Place
- Newport, RI (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 18065050
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S22: GENERAL STUDIES OF NUCLEAR REACTORS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ATWS; AUTOMATION; BLOWDOWN; COOLING; FEEDWATER; LOSSES; ON-LINE CONTROL SYSTEMS; OPERATION; OYSTER CREEK-1 REACTOR; POWER GENERATION; PUMPS; R CODES; REACTOR CORES; REACTOR SAFETY; REACTOR SHUTDOWN; STEAM LINES; VALVES; VAPOR CONDENSERS
- Descriptors DEC
- ACCIDENTS; BWR TYPE REACTORS; COMPUTER CODES; CONTROL EQUIPMENT; CONTROL SYSTEMS; DESIGN BASIS ACCIDENTS; ENRICHED URANIUM REACTORS; EQUIPMENT; FLOW REGULATORS; HYDROGEN COMPOUNDS; ON-LINE SYSTEMS; OXYGEN COMPOUNDS; PIPELINES; POLAR SOLVENTS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SAFETY; SHUTDOWN; SOLVENTS; THERMAL REACTORS; WATER; WATER COOLED REACTORS; WATER MODERATED REACTORS