Savannah River Site K-Reactor Probabilistic Safety Assessment
- Westinghouse Savannah River Co., Aiken, SC (United States)
- Science Applications International Corp. (United States)
This report gives the results of a Savannah River Site (SRS) K-Reactor Probabilistic Safety Assessment (PSA). Measures of adverse consequences to health and safety resulting from representations of severe accidents in SRS reactors are presented. In addition, the report gives a summary of the methods employed to represent these accidents and to assess the resultant consequences. The report is issued to provide useful information to the U. S. Department of Energy (DOE) on the risk of operation of SRS reactors, for insights into severe accident phenomena that contribute to this risk, and in support of improved bases for other DOE programs in Heavy Water Reactor safety.
- Research Organization:
- Westinghouse Savannah River Co., Aiken, SC (United States)
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC09-89SR18035
- OSTI ID:
- 10182116
- Report Number(s):
- WSRC-RP--91-041; ON: DE93040087
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600
220900
99 GENERAL AND MISCELLANEOUS
990200
CONTAINMENT SYSTEMS
CONTAMINATION
CORIUM
CRITICALITY
DATA COVARIANCES
ECONOMICS
EXPLOSIONS
FISSION PRODUCT RELEASE
FUEL ELEMENTS
FUEL-COOLANT INTERACTIONS
HEAT TRANSFER
HYDRAULICS
K REACTOR
LOSS OF COOLANT
M CODES
MATHEMATICS AND COMPUTERS
MELTDOWN
PUBLIC HEALTH
RADIATION DOSES
RADIATION TRANSPORT
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
RESEARCH
TEST
TRAINING
PRODUCTION
IRRADIATION
MATERIALS TESTING REACTORS
RISK ASSESSMENT
SAFETY ANALYSIS
SAVANNAH RIVER PLANT
SEISMIC EFFECTS
SOURCE TERMS
STEAM
SYSTEMS ANALYSIS
TRITIUM
220600
220900
99 GENERAL AND MISCELLANEOUS
990200
CONTAINMENT SYSTEMS
CONTAMINATION
CORIUM
CRITICALITY
DATA COVARIANCES
ECONOMICS
EXPLOSIONS
FISSION PRODUCT RELEASE
FUEL ELEMENTS
FUEL-COOLANT INTERACTIONS
HEAT TRANSFER
HYDRAULICS
K REACTOR
LOSS OF COOLANT
M CODES
MATHEMATICS AND COMPUTERS
MELTDOWN
PUBLIC HEALTH
RADIATION DOSES
RADIATION TRANSPORT
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
RESEARCH
TEST
TRAINING
PRODUCTION
IRRADIATION
MATERIALS TESTING REACTORS
RISK ASSESSMENT
SAFETY ANALYSIS
SAVANNAH RIVER PLANT
SEISMIC EFFECTS
SOURCE TERMS
STEAM
SYSTEMS ANALYSIS
TRITIUM