Assessment of RELAP5/MOD2, Cycle 36.02, using NEPTUN reflooding experimental data

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

OSTI ID:10176395

Richner, M; Analytis, G T; Aksan, S N ^[1]

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1. Paul Scherrer Inst. (PSI), Villigen (Switzerland)

This report discusses seven NEPTUN reflooding experiments with varying parameters flooding rate, single rod power, pressure and initial rod temperatures which were simulated with the code RELAP5/MOD2, version 36.02, to assess the code, especially its reflood model. These calculations were performed with the specific objectives of evaluating the general prediction capability as well as specific problem areas of the RELAP5/Mod2 code in modelling boil-off and reflood behavior. First a study of the effect of the hydraulic and conduction nodalization to the results of the code was performed using a high and a low flooding rate experiment. After the choice of a proper nodalization, base case calculations were done for all seven NEPTUN reflooding tests. The differences between code predictions and experiments are described and analysed. Implementing new correlations into the code and modifying or correcting existing correlations, for example for wall heat transfer or interphase friction, some of the weak points of the code during reflooding could be identified. These modifications were checked with all seven NEPTUN experiments. Additionally, two FLECHT-SEASET tests were simulated with the frozen version and also with the modifications mentioned above.

• 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: 10176395
• Report Number(s): NUREG/IA--0054; ON: TI92040398
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200
99 GENERAL AND MISCELLANEOUS
990200
BOILING
COMPUTER CALCULATIONS
COMPUTER PROGRAM DOCUMENTATION
HEAT TRANSFER
HYDRAULICS
MATHEMATICS AND COMPUTERS
MODIFICATIONS
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED
PWR TYPE REACTORS
R CODES
TEST FACILITIES
WATERFLOODING