Benchmarking the RELAP5/MOD2. 5 r-. Theta. model of an SRS (Savannah River Site) reactor to the 1989 L-Reactor tests
Conference
·
OSTI ID:6302170
- Westinghouse Savannah River Co., Aiken, SC (USA)
- 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
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220700 -- Nuclear Reactor Technology-- Plutonium & Isotope Production Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
ACCIDENTS
BENCHMARKS
COMPUTER CODES
COOLING SYSTEMS
DATA ANALYSIS
ENERGY SYSTEMS
ENERGY TRANSFER
FLOW MODELS
FLUID FLOW
FLUID MECHANICS
HEAT TRANSFER
HEAVY WATER MODERATED REACTORS
HYDRAULICS
L REACTOR
LOSS OF COOLANT
MATHEMATICAL MODELS
MECHANICS
NATIONAL ORGANIZATIONS
PRODUCTION REACTORS
R CODES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTORS
SAFETY
SAVANNAH RIVER PLANT
SPECIAL PRODUCTION REACTORS
TWO-PHASE FLOW
US AEC
US DOE
US ERDA
US ORGANIZATIONS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220700 -- Nuclear Reactor Technology-- Plutonium & Isotope Production Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
ACCIDENTS
BENCHMARKS
COMPUTER CODES
COOLING SYSTEMS
DATA ANALYSIS
ENERGY SYSTEMS
ENERGY TRANSFER
FLOW MODELS
FLUID FLOW
FLUID MECHANICS
HEAT TRANSFER
HEAVY WATER MODERATED REACTORS
HYDRAULICS
L REACTOR
LOSS OF COOLANT
MATHEMATICAL MODELS
MECHANICS
NATIONAL ORGANIZATIONS
PRODUCTION REACTORS
R CODES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTORS
SAFETY
SAVANNAH RIVER PLANT
SPECIAL PRODUCTION REACTORS
TWO-PHASE FLOW
US AEC
US DOE
US ERDA
US ORGANIZATIONS