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Fission product release characteristics into containment under design basis and severe accident conditions

Technical Report ·
DOI:https://doi.org/10.2172/6956680· OSTI ID:6956680
; ;
A detailed review of the radiological release estimates for light water reactor accident sequences is presented as a basis for development of a simplified approach for prediction of characteristics of radiological releases into containments under design basis and severe accident conditions for both Pressurized Water Reactors (PWRs) and Boiling Water Reactors (BWRs). Resulting source term estimates are also compared with parallel results using the Source Term Code Package (STCP) methodology.
Research Organization:
Nuclear Regulatory Commission, Washington, DC (USA). Office of Nuclear Regulatory Research; Brookhaven National Lab., Upton, NY (USA)
DOE Contract Number:
AC02-76CH00016
OSTI ID:
6956680
Report Number(s):
NUREG/CR-4881; BNL-NUREG-52059; ON: TI88010887
Country of Publication:
United States
Language:
English

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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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ACCIDENTS
AEROSOLS
BUILDING MATERIALS
BWR TYPE REACTORS
C CODES
COLLOIDS
COMPUTER CODES
CONCRETES
CONTAINMENT
COOLING SYSTEMS
CORIUM
DESIGN BASIS ACCIDENTS
DISPERSIONS
ENERGY SYSTEMS
ENERGY TRANSFER
FISSION PRODUCT RELEASE
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
I CODES
MATERIALS
MECHANICS
PWR TYPE REACTORS
RADIOACTIVE EFFLUENTS
RADIOACTIVE MATERIALS
RADIOACTIVE WASTES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORE DISRUPTION
REACTOR SAFETY
REACTORS
S CODES
SAFETY
SOLS
SOURCE TERMS
WASTES
WATER COOLED REACTORS
WATER MODERATED REACTORS