An assessment of RELAP5/MOD2 applicability to loss-of-feedwater transient analysis in a Babcock and Wilcox reactor plant
The applicability and scaling capability of RELAP5/MOD2 when applied to a Babcock and Wilcox (B and W) loss-of-feedwater transient is assessed using a code applicability methodology. A loss-of-feedwater test with a feed-and-bleed recovery was selected from the once-through integral system (OTIS) test data as a reference transient. Nondimensional comparisons are made between code assessment calculations and code applications calculations using computer code models scaled according to scaling criteria derived from the work of Ishii and others. The results indicate that RELAP5/MOD2 can scale the phenomena observed in the experiment and that the code is applicable for transients for which phenomena are within this envelope. The results also demonstrate the usefulness of the code applicability methodology for interpreting and verifying code calculations. 21 refs., 59 figs., 12 tabs.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (USA). Div. of Systems Research; EG and G Idaho, Inc., Idaho Falls (USA)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 6324030
- Report Number(s):
- NUREG/CR-5311; EGG-2560; ON: TI89008299
- Country of Publication:
- United States
- Language:
- English
Similar Records
Pre- and post-test analysis of LOBI MOD2 Test ST-02 (BT-00) with RELAP5/MOD1 and MOD2 (loss of feed water)
Pre- and post-test analysis of LOBI MOD2 Test ST-02 (BT-00) with RELAP5/MOD1 and MOD2 (loss of feed water)
RELAP5/MOD2 code assessment
Technical Report
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Tue Mar 31 23:00:00 EST 1992
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OSTI ID:10148173
Pre- and post-test analysis of LOBI MOD2 Test ST-02 (BT-00) with RELAP5/MOD1 and MOD2 (loss of feed water)
Technical Report
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Tue Mar 31 23:00:00 EST 1992
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OSTI ID:5244053
RELAP5/MOD2 code assessment
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Thu Oct 31 23:00:00 EST 1985
· Trans. Am. Nucl. Soc.; (United States)
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OSTI ID:5592524
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
99 GENERAL AND MISCELLANEOUS
990220 -- Computers
Computerized Models
& Computer Programs-- (1987-1989)
ACCIDENTS
COMPUTER CALCULATIONS
COMPUTER CODES
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
EVALUATION
FEEDWATER
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
HYDROGEN COMPOUNDS
LOSS OF COOLANT
MECHANICS
OXYGEN COMPOUNDS
PWR TYPE REACTORS
R CODES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTORS
RECOMMENDATIONS
SAFETY
TRANSIENTS
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
99 GENERAL AND MISCELLANEOUS
990220 -- Computers
Computerized Models
& Computer Programs-- (1987-1989)
ACCIDENTS
COMPUTER CALCULATIONS
COMPUTER CODES
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
EVALUATION
FEEDWATER
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
HYDROGEN COMPOUNDS
LOSS OF COOLANT
MECHANICS
OXYGEN COMPOUNDS
PWR TYPE REACTORS
R CODES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTORS
RECOMMENDATIONS
SAFETY
TRANSIENTS
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS