Analysis of a SBLOCA initiated by an ATWS event

Conference · Tue Jan 01 00:00:00 EST 1985

OSTI ID:5761556

Pu, J; Diamond, D J; Shier, W G

The response of a four-loop Westinghouse pressurized water reactor to SBLOCAs initiated as a result of an anticipated transient without scram (ATWS) has been analyzed using the RELAP5 computer code. The ATWS is initiated by a loss-of-feedwater, and the small breaks were due to either one or three stuck-open safety valves or reactor coolant pump seal failure. For the cases analyzed, the results show that a LOF-ATWS followed by a SBLOCA does not have more safety significance than that found when each accident is analyzed independently of one another.

• Research Organization: Brookhaven National Lab., Upton, NY (USA)
• DOE Contract Number: AC02-76CH00016
• OSTI ID: 5761556
• Report Number(s): BNL-NUREG-36009; CONF-850646-1; ON: TI85007483
• Resource Relation: Conference: 2. international specialists meeting on small break LOCA analyses in LWRs, Pisa, Italy, 24 Jun 1985
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
ATWS
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
PWR TYPE REACTORS
COMPUTER CODES
PRESSURE GRADIENTS
PUMPS
REACTOR SAFETY
SEALS
SYSTEM FAILURE ANALYSIS
VALVES
ACCIDENTS
CONTROL EQUIPMENT
ENERGY TRANSFER
EQUIPMENT
FLOW REGULATORS
FLUID MECHANICS
MECHANICS
REACTOR ACCIDENTS
REACTORS
SAFETY
SYSTEMS ANALYSIS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled