TRAC loss-of-coolant accident analyses of the Savannah River production reactors

Conference · Fri Jun 01 00:00:00 EDT 1990 · Transactions of the American Nuclear Society; (USA)

OSTI ID:6021913

Lime, J F; Motley, F E ^[1]

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1. Los Alamos National Lab., NM (USA)

TRAC loss-of-coolant accident (LOCA) analyses were performed as part of the independent safety review of the US Department of Energy's Savannah River (SR) production reactors. The double-ended guillotine break in a coolant loop is a design-basis LOCA for the SR reactors. Three break locations were analyzed to determine the worst break location: (1) at the pump-suction flange; (2) at the pump discharge flange; or (3) at the plenum inlet. The plenum-inlet break was shown to be the most severe in terms of minimum flow delivered to each fuel assembly in the reactor core.

• OSTI ID: 6021913
• Report Number(s): CONF-900608-; CODEN: TANSA; TRN: 91-008357
• Journal Information: Transactions of the American Nuclear Society; (USA), Vol. 61; Conference: American Nuclear Society (ANS) annual meeting, Nashville, TN (USA), 10-14 Jun 1990; ISSN 0003-018X
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
LOSS OF COOLANT
HEAT TRANSFER
HYDRAULICS
T CODES
SPECIAL PRODUCTION REACTORS
REACTOR SAFETY
BENCHMARKS
ECCS
FUEL ASSEMBLIES
PRIMARY COOLANT CIRCUITS
REACTOR ACCIDENTS
RUPTURES
THREE-DIMENSIONAL CALCULATIONS
US DOE
ACCIDENTS
COMPUTER CODES
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
FAILURES
FLUID MECHANICS
MECHANICS
NATIONAL ORGANIZATIONS
PRODUCTION REACTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR PROTECTION SYSTEMS
REACTORS
SAFETY
US ORGANIZATIONS
220900* - Nuclear Reactor Technology- Reactor Safety
220700 - Nuclear Reactor Technology- Plutonium & Isotope Production Reactors