Analysis of Semiscale test S-LH-1 using RELAP5/MOD2

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

OSTI ID:10146168

Hall, P C; Bull, D R ^[1]

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1. 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: Nuclear Regulatory Commission, Washington, DC (United States)
• OSTI ID: 10146168
• 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

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220200
220900
99 GENERAL AND MISCELLANEOUS
990200
COMPONENTS AND ACCESSORIES
COMPUTERIZED SIMULATION
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MATHEMATICS AND COMPUTERS
PRESSURIZERS
R CODES
REACTOR SAFETY
SIZEWELL-B REACTOR
TEST FACILITIES
TRANSIENTS
VALIDATION