Assessment of RELAP5/MOD2 against natural circulation experiments performed with the REWET-III facility
Technical Report
·
OSTI ID:5586936
- Valtion Teknillinen Tutkimuskeskus, Helsinki (Finland). Nuclear Engineering Lab.
Natural circulation experiments carried out in the REWET-III facility in 1985 have been used for RELAP5/MOD2 assessment. The REWET-III facility is a scaled-down model of VVER-440 type reactors. The facility consists of a pressure vessel in which the downcomer is simulated with an external pipe assembly, hot and cold legs with loop seals and a horizontal steam generator. The volume scaling factor compared to the reference reactor is 1:2333. The present paper summarizes the experiences gained in the RELAP5/MOD2 calculations of selected REWET-III single- and two-phase natural circulation experiments. The code's ability to represent the main phenomena of experiments in both cases was satisfactory.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (United States). Office of Nuclear Regulatory Research; Valtion Teknillinen Tutkimuskeskus, Helsinki (Finland). Nuclear Engineering Lab.
- Sponsoring Organization:
- USNRC; Nuclear Regulatory Commission, Washington, DC (United States)
- OSTI ID:
- 5586936
- Report Number(s):
- NUREG/IA-0059; ON: TI92013004
- Country of Publication:
- United States
- Language:
- English
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PWR TYPE REACTORS
REACTOR COOLING SYSTEMS
SCALE MODELS
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HEAT TRANSFER
HYDRAULICS
INTERNATIONAL COOPERATION
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COOLING SYSTEMS
COOPERATION
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FLUID FLOW
FLUID MECHANICS
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POWER REACTORS
REACTOR COMPONENTS
REACTORS
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SIMULATION
STRUCTURAL MODELS
THERMAL REACTORS
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220900* - Nuclear Reactor Technology- Reactor Safety
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990200 - Mathematics & Computers
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
PWR TYPE REACTORS
REACTOR COOLING SYSTEMS
SCALE MODELS
COMPUTERIZED SIMULATION
HEAT TRANSFER
HYDRAULICS
INTERNATIONAL COOPERATION
LOVIISA-1 REACTOR
LOVIISA-2 REACTOR
PRESSURE VESSELS
R CODES
REACTOR ACCIDENTS
REACTOR SAFETY
STEAM GENERATORS
TWO-PHASE FLOW
ACCIDENTS
BOILERS
COMPUTER CODES
CONTAINERS
COOLING SYSTEMS
COOPERATION
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FLUID FLOW
FLUID MECHANICS
MECHANICS
POWER REACTORS
REACTOR COMPONENTS
REACTORS
SAFETY
SIMULATION
STRUCTURAL MODELS
THERMAL REACTORS
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
WWER TYPE REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
990200 - Mathematics & Computers