TRAC-PD2 and RELAP5/MOD1 predictions of heated rod bundle experiments
Conference
·
OSTI ID:6592093
Neither code adequately predicts the subcooled boiling region of the flow: In (D-PD2, this is due to an inadequacy in the subcooled boiling model, in RELAP5/MOD1, this is due to a lack of the corresponding model. RELAP5/MOD1 predicts bulk boiling at conditions closer to equilibrium than TRAC-PD2. The codes use slighly different vertical flow region maps and correlations for interfacial friction; TRAC-PD2 predictions of the void distribution were in better agreement with the test data.
- Research Organization:
- Brookhaven National Lab., Upton, NY (USA)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 6592093
- Report Number(s):
- BNL-NUREG-29860; CONF-811103-28; ON: TI84017654
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
BHWR TYPE REACTORS
BOILING
COMPARATIVE EVALUATIONS
COMPUTER CODES
COMPUTERIZED SIMULATION
ENRICHED URANIUM REACTORS
FLUID FLOW
FUEL ASSEMBLIES
HEAVY WATER COOLED REACTORS
HEAVY WATER MODERATED REACTORS
MARVIKEN REACTOR
PHASE TRANSFORMATIONS
POWER REACTORS
REACTORS
SIMULATION
SUBCOOLED BOILING
TWO-PHASE FLOW
220900* -- Nuclear Reactor Technology-- Reactor Safety
BHWR TYPE REACTORS
BOILING
COMPARATIVE EVALUATIONS
COMPUTER CODES
COMPUTERIZED SIMULATION
ENRICHED URANIUM REACTORS
FLUID FLOW
FUEL ASSEMBLIES
HEAVY WATER COOLED REACTORS
HEAVY WATER MODERATED REACTORS
MARVIKEN REACTOR
PHASE TRANSFORMATIONS
POWER REACTORS
REACTORS
SIMULATION
SUBCOOLED BOILING
TWO-PHASE FLOW