Post-test-analysis and nodalization studies of OECD LOFT experiment LP-02-6 with RELAP5/Mod2 cy36-02
Technical Report
·
OSTI ID:7074024
- Paul Scherrer Inst. (PSI), Villigen (Switzerland)
Experiment LP-02-6 was conducted on October 3, 1983. It was the first large-break loss-of-coolant accident (LOCA) simulation and the fourth experiment at all conducted in the Loss-Of-Fluid-Test (LOFT) facility at the Idaho National Engineering Laboratory under the auspicies of the OECD. This experiment, which was designed to meet requirements outlined by the USNRC as specified in the OECD LOFT Project Agreement, simulated a double-ended off-set shear of a commercial pressurized water reactor (PWR) main coolant inlet pipe coincident with loss of offsite power. Experiment LP-02-6 addressed the response of a PWR to conditions closely resembling a USNRC Design Basis, Accident'' in that prepressurized fuel rods were installed and minimum US emergency coolant injections were used. This report presents the results and analysis of nine post-test calculations of the experiment LP-02-6 by using the RELAP5/Mod2 cy36-02 computer code with different nodalizations; these calculations have been performed within the International Code Assessment Program (ICAP) Starting with a standard nodalization'' as more or less used by the code developers at EG G, we have reduced the number of volumes and junctions (especially in the pressurizer, the steam generator secondary side and the intact loop) as well as the number of radial zones in the fuel rods, for different nodalization studies.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (United States). Office of Nuclear Regulatory Research; Paul Scherrer Inst. (PSI), Villigen (Switzerland)
- Sponsoring Organization:
- NRC; Nuclear Regulatory Commission, Washington, DC (United States)
- OSTI ID:
- 7074024
- Report Number(s):
- NUREG/IA-0088; PSI-Bericht-Nr--92; ON: TI92040320
- Country of Publication:
- United States
- Language:
- English
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99 GENERAL AND MISCELLANEOUS
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ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
FLUID MECHANICS
FUEL ELEMENTS
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
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POWER REACTORS
PRESSURIZERS
PWR TYPE REACTORS
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REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR PROTECTION SYSTEMS
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