Comparison of effluent and inlet header breaks for an SRS reactor LOPA

Conference · Wed Jan 01 04:00:00 EST 1992 · Transactions of the American Nuclear Society; (United States)

OSTI ID:6680928

Paul, P K; Barbour, K L; Herman, D T ^[1]

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1. Westinghouse Savannah River Co., Aiken, SC (United States)

The loss-of-pumping accident (LOPA) is a design-basis accident for Savannah River Site (SRS) reactors. The LOPA is defined as a double-ended guillotine break in a secondary cooling water pipe. The secondary cooling line break is termed inlet or effluent depending on break location. Upon break detection, the emergency shutdown procedure begins, the reactor scrams, the secondary cooling pump motors trip, the primary cooling pump alternating-current motors switch off, and the direct-current motor drive engages. Secondary cooling gravity flow continues flooding the building after the 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 because of 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.

• OSTI ID: 6680928
• Report Number(s): CONF-921102--
• Conference Information: Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 66
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
C REACTOR
COOLING SYSTEMS
DESIGN BASIS ACCIDENTS
FLUID MECHANICS
HEAVY WATER MODERATED REACTORS
HYDRAULICS
K REACTOR
L REACTOR
LOSS OF COOLANT
MECHANICS
P REACTOR
POWER DISTRIBUTION
PRODUCTION REACTORS
R REACTOR
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SHUTDOWN
REACTORS
SECONDARY COOLANT CIRCUITS
SHUTDOWN
SPECIAL PRODUCTION REACTORS
THERMAL ANALYSIS