Transient prediction of 19-tube once-through steam generator by RELAP5/MOD1
Conference
·
· Am. Soc. Mech. Eng., (Pap.); (United States)
OSTI ID:5691098
A simulation of Babcock and Wilcox's Alliance Research Center loss-of-feedwater of 19-tube model of once-through steam generator (OTSG) was performed with RELAP5/MOD1 and compared with the experimental data. Acceptable transient scenario was obtained when implementing Biasi and Macbeth critical heat flux correlations.
- Research Organization:
- Nuclear Power Generation, Babcock and Wilcox Co., Lynchburg, VA
- OSTI ID:
- 5691098
- Report Number(s):
- CONF-820705-
- Conference Information:
- Journal Name: Am. Soc. Mech. Eng., (Pap.); (United States) Journal Volume: 82-NE-15
- 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
ACCIDENTS
BOILERS
COMPUTER CODES
COMPUTERIZED SIMULATION
CRITICAL HEAT FLUX
FAILURES
FEEDWATER
HEAT FLUX
HYDROGEN COMPOUNDS
LOSS OF FLOW
LOSSES
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
OXYGEN COMPOUNDS
PARAMETRIC ANALYSIS
POWER PLANTS
R CODES
REACTOR ACCIDENTS
SIMULATION
STEAM GENERATORS
TESTING
THERMAL POWER PLANTS
TRANSIENTS
VAPOR GENERATORS
WATER
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BOILERS
COMPUTER CODES
COMPUTERIZED SIMULATION
CRITICAL HEAT FLUX
FAILURES
FEEDWATER
HEAT FLUX
HYDROGEN COMPOUNDS
LOSS OF FLOW
LOSSES
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
OXYGEN COMPOUNDS
PARAMETRIC ANALYSIS
POWER PLANTS
R CODES
REACTOR ACCIDENTS
SIMULATION
STEAM GENERATORS
TESTING
THERMAL POWER PLANTS
TRANSIENTS
VAPOR GENERATORS
WATER