Post-test analysis of LOBI test BT-12 using RELAP5/MOD2

Technical Report · Wed Apr 01 04:00:00 EST 1992

OSTI ID:10145842

Smethurst, A J ^[1]

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1. 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: Nuclear Regulatory Commission, Washington, DC (United States)
• OSTI ID: 10145842
• Report Number(s): NUREG/IA--0079; AEEW-R--2645; ON: TI92014120
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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22 GENERAL STUDIES OF NUCLEAR REACTORS
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99 GENERAL AND MISCELLANEOUS
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COMPUTER CALCULATIONS
HEAT LOSSES
HEAT TRANSFER
HYDRAULICS
INTERNATIONAL COOPERATION
LOSS OF COOLANT
MATHEMATICS AND COMPUTERS
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED
PWR TYPE REACTORS
R CODES
REACTOR SAFETY
RESEARCH PROGRAMS
SENSITIVITY ANALYSIS
STEAM GENERATORS
TEST FACILITIES