Post-test analysis of LOBI test BT-12 using RELAP5/MOD2
Technical Report
·
OSTI ID:5403118
- UKAEA Atomic Energy Establishment, Winfrith (United Kingdom)
This report describes calculations carried out with RELAP5/MOD2 on LOBI experiment BT-12, a large steam line break. The following sensitivity studies were performed: heat losses on the intact steam generator; discharge coefficient at break; water in steam lines; nearly implicit numerics. Qualitatively the general trends of BT-12 were predicted well, in particular the timing of events was fairly accurate.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (United States). Office of Nuclear Regulatory Research; UKAEA Atomic Energy Establishment, Winfrith (United Kingdom)
- Sponsoring Organization:
- NRC; Nuclear Regulatory Commission, Washington, DC (United States)
- OSTI ID:
- 5403118
- Report Number(s):
- NUREG/IA-0079; AEEW-R--2645; ON: TI92014120
- Country of Publication:
- United States
- Language:
- English
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Post-test analysis of LOBI test BT-12 using RELAP5/MOD2
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Pre- and post-test analysis of LOBI MOD2 Test ST-02 (BT-00) with RELAP5/MOD1 and MOD2 (loss of feed water)
Technical Report
·
Tue Mar 31 23:00:00 EST 1992
·
OSTI ID:10145842
Pre- and post-test analysis of LOBI MOD2 Test ST-02 (BT-00) with RELAP5/MOD1 and MOD2 (loss of feed water)
Technical Report
·
Tue Mar 31 23:00:00 EST 1992
·
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
·
Tue Mar 31 23:00:00 EST 1992
·
OSTI ID:5244053
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210200 -- Power Reactors
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22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
ACCIDENTS
BOILERS
COMPUTER CALCULATIONS
COMPUTER CODES
COOPERATION
ENERGY LOSSES
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FLUID MECHANICS
HEAT LOSSES
HEAT TRANSFER
HYDRAULICS
INTERNATIONAL COOPERATION
LOSS OF COOLANT
LOSSES
MECHANICS
POWER REACTORS
PWR TYPE REACTORS
R CODES
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
RESEARCH PROGRAMS
SAFETY
SENSITIVITY ANALYSIS
STEAM GENERATORS
TEST FACILITIES
THERMAL REACTORS
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS