Comparison of the RELAP5/MOD3 and RELAP5/MOD2 predictions of the Winfrith postdryout experiment
- Texas A and M Univ., College Station (United States)
The development and modification of any computer code necessitate assessment and validation of the code. A similar task prevails with the release of the thermal-hydraulic analysis code RELAP5/MOD3. RELAP5/MOD3 was developed by EG and G Idaho from its predecessor code RELAP5/MOD2 after identifying certain deficiencies in the latter. Among the various modifications is the new interfacial drag model. In this study, the RELAP5/MOD2 and RELAP5/MOD3 codes are used to predict the results of a steady-state postdryout experiment conducted at the Winfrith facility in the United Kingdom. The Winfrith test facility is used to perform postdryout experiments are relatively low heat fluxes and steam qualities.
- OSTI ID:
- 5977907
- Report Number(s):
- CONF-910603--
- Journal Information:
- Transactions of the American Nuclear Society; (United States), Journal Name: Transactions of the American Nuclear Society; (United States) Vol. 63; ISSN TANSA; ISSN 0003-018X
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
DRAG
DRYOUT
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FLOW RATE
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MECHANICS
MODIFICATIONS
POWER REACTORS
PWR TYPE REACTORS
QUENCHING
REACTOR ACCIDENTS
REACTOR SAFETY EXPERIMENTS
REACTORS
SURFACE PROPERTIES
SURFACE TENSION
TEST FACILITIES
TESTING
THERMAL REACTORS
TIME DEPENDENCE
TRANSIENTS
VALIDATION
VOID FRACTION
WATER COOLED REACTORS
WATER MODERATED REACTORS