Evaluation of the consequences of containment bypass scenarios
Fission product transport and deposition in auxiliary and secondary containment buildings are important considerations in severe-accident analysis. Accordingly, a methodology has been developed that can be used to evaluate such fission product retention. Accident sequences considered include containment bypass scenarios and others that involve fission products being released from the containment into an adjacent building. The following were produced: (a) a list of plant-specific features that have a major influence of fission product retention; (b) a catalog of the pertinent auxiliary building/reactor building configurations sufficient to allow utilities to perform their own analyses; (c) a model for the building circulatory flows, both natural and forced, which allows arbitrary nodalization and has been experimentally verified; and (d) analyses of the sequences for the major variations in design. Fission product releases to the environment are principally governed by building response. Other important factors include the following: (1) auxiliary building size; (2) building compartmentalization and position of door jambs; (3) junction flow area to the environment; (4) operability of ventilation systems; (5) scrubbing through water pools covering the release point; (6) water sprays.
- OSTI ID:
- 5432218
- Report Number(s):
- CONF-881011-; CODEN: TANSA; TRN: 89-029043
- Journal Information:
- Transactions of the American Nuclear Society; (USA), Vol. 57; Conference: Joint meeting of the European Nuclear Society and the American Nuclear Society, Washington, DC (USA), 30 Oct - 4 Nov 1988; ISSN 0003-018X
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
CONTAINMENT SYSTEMS
BYPASSES
NUCLEAR POWER PLANTS
REACTOR SAFETY
REACTOR ACCIDENTS
RADIOACTIVITY TRANSPORT
BRINES
CESIUM IODIDES
COMPUTERIZED SIMULATION
DECONTAMINATION
DEPOSITION
DESIGN
ECCS
ENVIRONMENT
FILTERS
FISSION PRODUCTS
HYDROGEN
IGNITION
LOSS OF COOLANT
M CODES
NATURAL CONVECTION
PARAMETRIC ANALYSIS
PIPES
PRIMARY COOLANT CIRCUITS
PUMPS
RHR SYSTEMS
RUPTURES
SOURCE TERMS
ACCIDENTS
ALKALI METAL COMPOUNDS
CESIUM COMPOUNDS
CLEANING
COMPUTER CODES
CONTAINMENT
CONVECTION
COOLING SYSTEMS
ELEMENTS
ENERGY SYSTEMS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
FAILURES
HALIDES
HALOGEN COMPOUNDS
HEAT TRANSFER
INORGANIC PHOSPHORS
IODIDES
IODINE COMPOUNDS
ISOTOPES
MASS TRANSFER
MATERIALS
NONMETALS
NUCLEAR FACILITIES
PHOSPHORS
POWER PLANTS
RADIOACTIVE MATERIALS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR PROTECTION SYSTEMS
SAFETY
SIMULATION
THERMAL POWER PLANTS
220900* - Nuclear Reactor Technology- Reactor Safety