Source term calculation for a small LOCA sequence in a VVER-1000-type reactor
Two years ago, a program was initiated to investigate the behavior of fission products and aerosols generated during a severe accident in a VVER-1000-type reactor. The Source Term Code Package was selected to perform the calculation. In a first step, no specific power plant was considered, and the input data were based only on typical VVER-1000 features. The results for a transient-initiated event with failure of all makeup to the primary and secondary systems as well as the failure of all active containment safety features showed a fission product behavior quite similar to that in a Western-type reactor. The next steps were the improvement of the basic input data and the calculation for a different accident sequence. Zaporozhye-5 was selected as the reference plant. The accident is initiated by an 80-mm-diam small-break loss-of-coolant accident (LOCA) in the hot leg followed by loss of off-site and on-site electric power (S[sub 1] B sequence). Recently performed probabilistic safety assessments for VVER-440 plants show that this sequence makes a large contribution to core melt frequency.
- OSTI ID:
- 6780189
- Report Number(s):
- CONF-901101--
- Journal Information:
- Transactions of the American Nuclear Society; (United States), Journal Name: Transactions of the American Nuclear Society; (United States) Vol. 62; ISSN 0003-018X; ISSN TANSAO
- Country of Publication:
- United States
- Language:
- English
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22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
AEROSOLS
BLACKOUTS
COLLOIDS
COMPUTER CALCULATIONS
CONTAINMENT
CONTAINMENT SYSTEMS
COOLING SYSTEMS
DISPERSIONS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
FISSION PRODUCT RELEASE
FLUID MECHANICS
FREQUENCY ANALYSIS
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MECHANICS
POWER REACTORS
PRIMARY COOLANT CIRCUITS
PROBABILISTIC ESTIMATION
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORE DISRUPTION
REACTORS
RISK ASSESSMENT
SECONDARY COOLANT CIRCUITS
SOLS
SOURCE TERMS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
WWER TYPE REACTORS
ZAPOROZHE-1 REACTOR
ZAPOROZHE-2 REACTOR
ZAPOROZHE-3 REACTOR
ZAPOROZHE-4 REACTOR