Analysis of fission product revaporization in a BWR reactor cooling system during a station blackout accident
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5781153
A preliminary analysis of the re-evaporization of volatile fission product from a boiling water reactor (BWR) cooling system following a core meltdown accident in which the core debris penetrates the reactor vessel has been performed. The BWR analyzed has a Mark I containment and the accident sequence was a station blackout transient. This work was performed as part of the phenomenological uncertainty study of the Quantification and Uncertainty Analysis of Source Terms for Severe Accidents program at Brookhaven National Laboratory. Fission product re-evaporization was identified as one of the important issues in the Reactor Risk Reference Document.
- Research Organization:
- Brookhaven National Lab., Upton, NY (USA)
- OSTI ID:
- 5781153
- Report Number(s):
- CONF-881011-
- Journal Information:
- Trans. Am. Nucl. Soc.; (United States), Vol. 57; Conference: Joint meeting of the European Nuclear Society and the American Nuclear Society, Washington, DC, USA, 30 Oct - 4 Nov 1988
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
REACTOR SAFETY
FISSION PRODUCTS
EVAPORATION
PRIMARY COOLANT CIRCUITS
REACTOR CORE DISRUPTION
SOURCE TERMS
BNL
CESIUM HYDROXIDES
CESIUM IODIDES
CHEMISORPTION
CONTAINMENT SYSTEMS
CORIUM
DECAY
HEAT TRANSFER
HYDRAULICS
OUTAGES
PRESSURE VESSELS
REACTOR ACCIDENTS
RISK ASSESSMENT
TELLURIUM
ACCIDENTS
ALKALI METAL COMPOUNDS
CESIUM COMPOUNDS
CHEMICAL REACTIONS
CONTAINERS
CONTAINMENT
COOLING SYSTEMS
ELEMENTS
ENERGY SYSTEMS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
FLUID MECHANICS
HALIDES
HALOGEN COMPOUNDS
HYDROGEN COMPOUNDS
HYDROXIDES
INORGANIC PHOSPHORS
IODIDES
IODINE COMPOUNDS
ISOTOPES
MATERIALS
MECHANICS
NATIONAL ORGANIZATIONS
OXYGEN COMPOUNDS
PHASE TRANSFORMATIONS
PHOSPHORS
RADIOACTIVE MATERIALS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
SAFETY
SEMIMETALS
SEPARATION PROCESSES
SORPTION
US AEC
US DOE
US ERDA
US ORGANIZATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
REACTOR SAFETY
FISSION PRODUCTS
EVAPORATION
PRIMARY COOLANT CIRCUITS
REACTOR CORE DISRUPTION
SOURCE TERMS
BNL
CESIUM HYDROXIDES
CESIUM IODIDES
CHEMISORPTION
CONTAINMENT SYSTEMS
CORIUM
DECAY
HEAT TRANSFER
HYDRAULICS
OUTAGES
PRESSURE VESSELS
REACTOR ACCIDENTS
RISK ASSESSMENT
TELLURIUM
ACCIDENTS
ALKALI METAL COMPOUNDS
CESIUM COMPOUNDS
CHEMICAL REACTIONS
CONTAINERS
CONTAINMENT
COOLING SYSTEMS
ELEMENTS
ENERGY SYSTEMS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
FLUID MECHANICS
HALIDES
HALOGEN COMPOUNDS
HYDROGEN COMPOUNDS
HYDROXIDES
INORGANIC PHOSPHORS
IODIDES
IODINE COMPOUNDS
ISOTOPES
MATERIALS
MECHANICS
NATIONAL ORGANIZATIONS
OXYGEN COMPOUNDS
PHASE TRANSFORMATIONS
PHOSPHORS
RADIOACTIVE MATERIALS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
SAFETY
SEMIMETALS
SEPARATION PROCESSES
SORPTION
US AEC
US DOE
US ERDA
US ORGANIZATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled