Effluent versus inlet header break analysis for SRS-reactor LOPA scenario
Conference
·
OSTI ID:7031715
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:
- DOE; 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
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220200* -- Nuclear Reactor Technology-- Components & Accessories
220504 -- Nuclear Reactor Technology-- Environmental Aspects-- Design Basis & Hypothetical Accidents-- (1992-)
220900 -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
COOLING SYSTEMS
DESIGN BASIS ACCIDENTS
NATIONAL ORGANIZATIONS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTORS
RISK ASSESSMENT
SAFETY
SAVANNAH RIVER PLANT
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
ACCIDENTS
COOLING SYSTEMS
DESIGN BASIS ACCIDENTS
NATIONAL ORGANIZATIONS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTORS
RISK ASSESSMENT
SAFETY
SAVANNAH RIVER PLANT
US AEC
US DOE
US ERDA
US ORGANIZATIONS