RELAP5/MOD2 calculation of OECD LOFT test LP-FW-01

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

OSTI ID:10146314

Croxfod, M G; Harwood, C; Hall, P C ^[1]

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1. National Power Nuclear, Barnwood (United Kingdom)

RELAP5/MOD2 is being used by GDCD for calculation of certain small break loss-of-coolant accidents and pressurized transients in the Sizewell ``B`` PWR. To test the ability of RELAP5/MOD2 to model the primary feed-and-bleed recovery procedure following a complete loss- of-feedwater event, post test calculations have been carried out of OECD LOFT test LP-FW-01. This report describes the comparison between the code calculations and the test data. It is found that although the standard version of RELAP5/MOD2 gives a reasonable prediction of the experimental transient, the long term pressure history is better calculated with a modified code version containing a revised horizontal stratification entrainment model. The latter allows an improved calculation of entrainment of liquid from the hot leg into the surge line. RELAP5/MOD2 is found to give a more accurate simulation of the experimental transient than was achieved in previous UK studies using RETRAN-02/MOD2.

• 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: 10146314
• Report Number(s): NUREG/IA--0063; GD/PE-N--597; ON: TI92014221
• Country of Publication: United States
• Language: English

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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
COMPUTERIZED SIMULATION
HEAT TRANSFER
HYDRAULICS
INTERNATIONAL COOPERATION
LOFT REACTOR
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MATHEMATICS AND COMPUTERS
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PWR TYPE REACTORS
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REACTOR SAFETY
RESEARCH PROGRAMS
STEAM GENERATORS
TEST FACILITIES