Evaluation of the consequences of containment bypass scenarios
Creators
Description
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
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 57
- Series
- Trans. Am. Nucl. Soc.
- Journal Page Range
- 194-195
- ISSN
- 0003-018X
- CODEN
- TANSA
Conference
- Title
- Joint meeting of the European Nuclear Society and the American Nuclear Society.
- Dates
- 30 Oct - 4 Nov 1988.
- Place
- Washington, DC (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 21014179
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AFTER-HEAT REMOVAL; BRINES; BYPASSES; CESIUM IODIDES; COMBUSTION; COMPUTERIZED SIMULATION; CONTAINMENT SYSTEMS; DECONTAMINATION; DEPOSITION; ECCS; ENVIRONMENT; FILTERS; FISSION PRODUCTS; HYDROGEN; LOSS OF COOLANT; M CODES; MULTI-PARAMETER ANALYSIS; NATURAL CONVECTION; NUCLEAR POWER PLANTS; PIPES; PRIMARY COOLANT CIRCUITS; PUMPS; RADIOACTIVITY TRANSPORT; REACTOR ACCIDENTS; REACTOR SAFETY; RUPTURES; SOURCE TERMS; SPECIFICATIONS
- Descriptors DEC
- ACCIDENTS; ALKALI METAL COMPOUNDS; CESIUM COMPOUNDS; CHEMICAL REACTIONS; CLEANING; COMPUTER CODES; CONTAINMENT; CONVECTION; COOLING SYSTEMS; ELEMENTS; ENERGY TRANSFER; EQUIPMENT; FAILURES; HALIDES; HALOGEN COMPOUNDS; HEAT TRANSFER; IODIDES; IODINE COMPOUNDS; ISOTOPES; MATERIALS; NONMETALS; NUCLEAR FACILITIES; OXIDATION; POWER PLANTS; RADIOACTIVE MATERIALS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTOR PROTECTION SYSTEMS; SAFETY; SIMULATION; THERMAL POWER PLANTS
Optional Information
- Secondary number(s)
- CONF-881011--.