Analysis of Semiscale test S-LH-1 using RELAP5/MOD2
- National Power Nuclear, Barnwood (United Kingdom)
The RELAP5/MOD2 code is being used by GDCD for calculating Small Break Loss of Coolant Accidents (SBLOCA) and pressurized transient sequences for the Sizewell B'' PWR. These calculations are being carried out at the request of Sizewell B'' Project Management Team. To assist in validating RELAP5/MOD2 for the above application, the code is being used by GDCD to model a number of small LOCA and pressurized fault simulation experiments carried out in various integral test facilities. The present report describes a RELAP5/MOD2 analysis of the small LOCA test S-LH-1 which was performed on the Semiscale Mod-2C facility. S-LH-1 simulated a small LOCA caused by a break in the cold leg pipework of an area equal to 5% of the cold leg flow area.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (United States). Office of Nuclear Regulatory Research; National Power Nuclear, Barnwood (United Kingdom)
- Sponsoring Organization:
- USNRC; Nuclear Regulatory Commission, Washington, DC (United States)
- OSTI ID:
- 5333885
- Report Number(s):
- NUREG/IA-0064; GD/PE-N-725; PWR/HTWG/P-(88)629(Rev); ON: TI92014290
- Country of Publication:
- United States
- Language:
- English
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Analysis of semiscale test S-LH-2 using RELAP5/MOD2
Analysis of semiscale test S-LH-2 using RELAP5/MOD2
Related Subjects
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
SIZEWELL-B REACTOR
TRANSIENTS
COMPUTERIZED SIMULATION
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
PRESSURIZERS
R CODES
REACTOR SAFETY
TEST FACILITIES
VALIDATION
ACCIDENTS
COMPUTER CODES
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FLUID MECHANICS
MECHANICS
POWER REACTORS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTORS
SAFETY
SIMULATION
TESTING
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
220200 - Nuclear Reactor Technology- Components & Accessories
990200 - Mathematics & Computers