Assessment of RELAP5/MOD2, Cycle 36-04 using LOFT (Loss of Fluid Test) Large Break Experiment L2-5
- Korea Advanced Energy Research Inst., Daeduk-Danji (Republic of Korea). Korea Nuclear Safety Center
The LOFT L2-5 LBLOCA Experiment was simulated using the RELAP5/MOD2 Cycle 36.04 code to assess its capability to predict the phenomena in LBLOCA. One base case calculation and three cases of different nodalizations were carried out. The effect of different nodalization was studied in the area of the downcomer and core. For a sensitivity study, another calculation was executed using an updated version of RELAP5/MOD2 Cycle 36.04. A Split downcomer with one crossflow junction and two core channels were found to be effective in describing the ECC bypass and hot channel behavior. And the updated version was found to be effective in overcoming the code deficiency in the interfacial friction and reflood quenching. 11 refs., 55 figs., 10 tabs.
- Research Organization:
- US Nuclear Regulatory Commission (NRC), Washington, DC (United States). Office of Nuclear Regulatory Research; Korea Advanced Energy Research Inst., Daeduk-Danji (Republic of Korea). Korea Nuclear Safety Center
- Sponsoring Organization:
- USNRC
- OSTI ID:
- 7038130
- Report Number(s):
- NUREG/IA-0032; ON: TI90009896; TRN: 90-011951
- Country of Publication:
- United States
- Language:
- English
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99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
LOFT REACTOR
LOSS OF COOLANT
COMPILED DATA
ECCS
HEAT TRANSFER
HYDRAULICS
R CODES
REACTOR CHANNELS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
SENSITIVITY ANALYSIS
ACCIDENTS
COMPUTER CODES
COOLING SYSTEMS
DATA
ENERGY SYSTEMS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
FLUID MECHANICS
INFORMATION
MECHANICS
NUMERICAL DATA
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR PROTECTION SYSTEMS
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
TANK TYPE REACTORS
TEST REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
990200 - Mathematics & Computers
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled