Analysis of CRBRP station blackout using SSC/MINET
A steam generator system transient analysis package (MINET), recently incorporated into the SSC code (a nuclear power plant systems analysis code), is reported. Essentially a code within a larger code, MINET is so named because it is based on a momentum integral network method. Since the SSC code is being used extensively in the analysis of the Clinch River Breeder Reactor Plant (CRBRP), an analysis of the CRBRP steam generator system, using MINET, is reported. Plant transient data are generally unavailable for such advanced power plants, therefore, results from computer analysis of a CRBRP station blackout event, using the DEMO code, are shown. Comparable SSC/MINET analysis provided similar results, particularly when two specific DEMO assumptions were factored into the MINET calculations. A more extensive SSC/MINET analysis of a CRBRP station blackout event, with pony motors and auxiliary feedwater pumps unavailable, is also reported.
- Research Organization:
- Brookhaven National Laboratory, Upton, NY
- OSTI ID:
- 5691110
- Report Number(s):
- CONF-820705-
- Journal Information:
- Am. Soc. Mech. Eng., (Pap.); (United States), Vol. 82-NE-19; Conference: 2. joint ASME/ANS nuclear engineering conference, Portland, OR, USA, 25 Jul 1982
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BLACKOUTS
COMPUTERIZED SIMULATION
CLINCH RIVER BREEDER REACTOR
STEAM GENERATORS
COMPUTER CODES
M CODES
ELECTRIC MOTORS
FEEDWATER
NUCLEAR POWER PLANTS
PUMPS
TRANSIENTS
BOILERS
BREEDER REACTORS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
HYDROGEN COMPOUNDS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MOTORS
NUCLEAR FACILITIES
OXYGEN COMPOUNDS
POWER PLANTS
POWER REACTORS
REACTORS
SIMULATION
SODIUM COOLED REACTORS
THERMAL POWER PLANTS
VAPOR GENERATORS
WATER
220900* - Nuclear Reactor Technology- Reactor Safety
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