RELAP5 modeling of a Savannah River Site reactor
Conference
·
OSTI ID:6287364
- Westinghouse Savannah River Co., Aiken, SC (USA)
- EG and G Idaho, Inc., Idaho Falls, ID (USA)
Thermal-hydraulic system analysis in support of Savannah River Site reactor restart is being performed with a modified version of RELAP5/MOD2.5. This paper gives an overview of the Savannah River Site reactor system, the RELAP5 input models developed for the analysis, and the specific phenomena with which the code is having difficulty. The need for code development to address plenum phenomena, air/water behavior, fuel assembly behavior, and degraded pump performance is motivated in terms of the system response to a large break loss-of-coolant accident. Results of benchmark calculations show both the adequacy of the basic models and the need for a better representation of phenomena that are beyond the typical range of RELAP5 application. 9 refs.
- Research Organization:
- Westinghouse Savannah River Co., Aiken, SC (USA)
- Sponsoring Organization:
- DOE/DP
- DOE Contract Number:
- AC09-89SR18035
- OSTI ID:
- 6287364
- Report Number(s):
- WSRC-MS-90-206; CONF-9009219--5; ON: DE91005664
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
42 ENGINEERING
420400 -- Engineering-- Heat Transfer & Fluid Flow
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
ACCIDENTS
BENCHMARKS
COMPUTER CODES
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FLUID MECHANICS
FUEL ASSEMBLIES
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MATHEMATICAL MODELS
MECHANICS
MODIFICATIONS
PERFORMANCE
PROPULSION REACTORS
PWR TYPE REACTORS
R CODES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
SAVANNAH REACTOR
SHIP PROPULSION REACTORS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
42 ENGINEERING
420400 -- Engineering-- Heat Transfer & Fluid Flow
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
ACCIDENTS
BENCHMARKS
COMPUTER CODES
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FLUID MECHANICS
FUEL ASSEMBLIES
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MATHEMATICAL MODELS
MECHANICS
MODIFICATIONS
PERFORMANCE
PROPULSION REACTORS
PWR TYPE REACTORS
R CODES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
SAVANNAH REACTOR
SHIP PROPULSION REACTORS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS