Benchmarking the RELAP5/MOD2. 5 r-. Theta. model of an SRS (Savannah River Site) reactor to the 1989 L-Reactor tests

Conference · Mon Jan 01 00:00:00 EST 1990

OSTI ID:6302170

Bollinger, J S ^[1]; Davis, C B ^[2]

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1. Westinghouse Savannah River Co., Aiken, SC (USA)
2. EG and G Idaho, Inc., Idaho Falls, ID (USA)

Benchmarking calculations utilizing RELAP5/MOD2.5 with a detailed multi-dimensional r-{theta} model of the SRS L-Reactor will be presented. This benchmarking effort has provided much insight into the two-component two-phase behavior of the reactor under isothermal conditions with large quantities of air ingested from the moderator tank to the external loops. Initial benchmarking results have illuminated several model weaknesses which will be discussed in conjunction with proposed modeling changes. The benchmarking work is being performed to provide a fully qualified RELAP5 model for use in computing the system response to a double ended large break LOCA. 5 refs., 14 figs.

• Research Organization: Westinghouse Savannah River Co., Aiken, SC (USA)
• Sponsoring Organization: DOE/DP
• DOE Contract Number: AC09-89SR18035
• OSTI ID: 6302170
• Report Number(s): WSRC-MS-90-203; CONF-9009219-6; ON: DE91007237; TRN: 91-004726
• Resource Relation: Conference: 1990 joint RELAP5 and TRAC-BWR international user seminar, Chicago, IL (USA), 17-21 Sep 1990
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
L REACTOR
LOSS OF COOLANT
BENCHMARKS
DATA ANALYSIS
FLOW MODELS
HEAT TRANSFER
HYDRAULICS
R CODES
REACTOR COOLING SYSTEMS
REACTOR SAFETY
SAVANNAH RIVER PLANT
TWO-PHASE FLOW
ACCIDENTS
COMPUTER CODES
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
FLUID FLOW
FLUID MECHANICS
HEAVY WATER MODERATED REACTORS
MATHEMATICAL MODELS
MECHANICS
NATIONAL ORGANIZATIONS
PRODUCTION REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
SAFETY
SPECIAL PRODUCTION REACTORS
US AEC
US DOE
US ERDA
US ORGANIZATIONS
220900* - Nuclear Reactor Technology- Reactor Safety
220700 - Nuclear Reactor Technology- Plutonium & Isotope Production Reactors
990200 - Mathematics & Computers