Post-test-analysis and nodalization studies of OECD LOFT experiment LP-02-6 with RELAP5/Mod2 cy36-02

Technical Report · Sat Aug 01 04:00:00 EDT 1992

OSTI ID:10174200

Luebbesmeyer, D ^[1]

---

1. 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: Nuclear Regulatory Commission, Washington, DC (United States)
• OSTI ID: 10174200
• Report Number(s): NUREG/IA--0088; PSI-Bericht-Nr--92; ON: TI92040320
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900
99 GENERAL AND MISCELLANEOUS
990200
DESIGN BASIS ACCIDENTS
ECCS
FUEL ELEMENTS
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MATHEMATICS AND COMPUTERS
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED
PRESSURIZERS
PWR TYPE REACTORS
R CODES
REACTOR COOLING SYSTEMS
REACTOR SAFETY
STEAM GENERATORS