Effluent versus inlet header break analysis for SRS-reactor LOPA scenario

Conference · Wed Jan 01 00:00:00 EST 1992

OSTI ID:7031715

Paul, P K; Barbour, K L; Herman, D T

The Loss-of-Pumping Accident (LOPA) is a design basis accident for the Savannah River Site (SRS) reactors. The LOPA is defined as a Double Ended Guillotine Break (DEGB) in a secondary cooling water pipe. The secondary cooling line break is termed inlet or effluent depending on break location. Upon break detection emergency shut down procedure begins, the reactor scrams, secondary cooling pump motors trip off, primary cooling pump AC motors switch off, and DC motor drive engages. Secondary cooling gravity flow continues flooding the building after secondary cooling pumps are off. The Emergency Cooling System (ECS) activates before the DC motors flood out. Break detection time, header flooding rate, and flooding locations are different for the inlet and effluent header breaks due to different break locations. Inlet and effluent header break primary coolant temperature transients differ because primary and secondary cooling pumps continue during a break detection and reactor scram time delay for the effluent header case, whereas the pumps trip off almost immediately for the inlet header case. Design basis accident reactor core power limits are calculated for both the inlet and effluent header breaks.

• Research Organization: Westinghouse Savannah River Co., Aiken, SC (United States)
• Sponsoring Organization: USDOE; USDOE, Washington, DC (United States)
• DOE Contract Number: AC09-89SR18035
• OSTI ID: 7031715
• Report Number(s): WSRC-MS-92-193; CONF-921102-7; ON: DE92016850
• Resource Relation: Conference: Joint American Nuclear Society/European Nuclear Society international meeting, Chicago, IL (United States), 15-20 Nov 1992
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
REACTOR COOLING SYSTEMS
DESIGN BASIS ACCIDENTS
SAVANNAH RIVER PLANT
REACTORS
REACTOR SAFETY
RISK ASSESSMENT
ACCIDENTS
COOLING SYSTEMS
NATIONAL ORGANIZATIONS
REACTOR ACCIDENTS
REACTOR COMPONENTS
SAFETY
US AEC
US DOE
US ERDA
US ORGANIZATIONS
220200* - Nuclear Reactor Technology- Components & Accessories
220504 - Nuclear Reactor Technology- Environmental Aspects- Design Basis & Hypothetical Accidents- (1992-)
220900 - Nuclear Reactor Technology- Reactor Safety