RELAP5/MOD2 calculation of OECD LOFT test LP-FW-01
Technical Report
·
OSTI ID:5347623
- 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:
- NRC; Nuclear Regulatory Commission, Washington, DC (United States)
- OSTI ID:
- 5347623
- Report Number(s):
- NUREG/IA-0063; GD/PE-N--597; ON: TI92014221
- Country of Publication:
- United States
- Language:
- English
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ACCIDENTS
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COMPUTER CALCULATIONS
COMPUTER CODES
COMPUTERIZED SIMULATION
COOPERATION
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
INTERNATIONAL COOPERATION
LOFT REACTOR
LOSS OF COOLANT
MECHANICS
POWER REACTORS
PWR TYPE REACTORS
R CODES
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH PROGRAMS
SAFETY
SIMULATION
STEAM GENERATORS
TANK TYPE REACTORS
TEST FACILITIES
TEST REACTORS
THERMAL REACTORS
VAPOR GENERATORS
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WATER MODERATED REACTORS