Loss of pumping accident limit calculation for Savannah River Reactor

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

OSTI ID:7055911

Paul, P K; Barbour, K L ^[1]

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

For the Savannah River Site production reactors, the design basis accident reactor power limit ensures that if a double-ended guillotine break (DEGB) in a secondary cooling water pipe were to occur, the reactor will shut down safely. The primary reactor coolant is heavy water (D{sub 2}O) with secondary light water (H{sub 2}O) cooling. The accident scenario is a DEGB in one of two secondary coolant inlet header pipes with several assumed single failures. The recycled primary coolant loses its cooling, and the reactor core temperature begins to rise. Another possible accident is a DEGB in one of two heat exchanger secondary coolant effluent header pipes. The inlet header break is slightly more limiting than the effluent header break. Upon break detection, emergency shutdown begins and the emergency cooling system (ECS) activates. The accident scenario was constructed with regard to physical, mechanical, and human factors. The computer code TRAC simulates the accident.

• OSTI ID: 7055911
• Report Number(s): CONF-920606--
• Conference Information: Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 65
• 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
AC SYSTEMS
ACCIDENTS
COOLING SYSTEMS
CRITICAL HEAT FLUX
DC SYSTEMS
ECCS
EMERGENCY PLANS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
FAILURES
FLOW RATE
FLUID MECHANICS
FUEL ASSEMBLIES
HEAT EXCHANGERS
HEAT FLUX
HEAT TRANSFER
HEAVY WATER
HYDRAULICS
HYDROGEN COMPOUNDS
LOSS OF COOLANT
LOSS OF FLOW
MECHANICS
MOTORS
NATIONAL ORGANIZATIONS
OXYGEN COMPOUNDS
PIPES
POWER SYSTEMS
PRIMARY COOLANT CIRCUITS
PRODUCTION REACTORS
PUMPS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORES
REACTOR MONITORING SYSTEMS
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTOR SHUTDOWN
REACTORS
RUPTURES
SAFETY
SAVANNAH RIVER PLANT
SCRAM
SECONDARY COOLANT CIRCUITS
SHUTDOWN
SPECIAL PRODUCTION REACTORS
STEADY-STATE CONDITIONS
TEMPERATURE DEPENDENCE
US AEC
US DOE
US ERDA
US ORGANIZATIONS
VOID FRACTION
WATER