Probabilistic Safety Assessment for the Savannah River Site K Reactor
- Westinghouse Savannah River Co., Aiken, SC (United States)
A probabilistic study of the overall safety of the special materials production reactors located at the US Department of Energy's Savannah River site (SRS) has been performed. Assessments of the risk associated with reactor operation that is posed to the work force at SRS and to the surrounding population are among the results obtained. Safety assessment methodology that has evolved from applications in the commercials nuclear power industry over the past 20 yr, and has recently been employed in two other major studies was used for the analysis. The results of the study indicate that risks from severe reactor accidents to individuals in the neighboring populace are within levels that have been found to be acceptable for commercial nuclear power plants. The objectives of the SRS probabilistic safety assessment (PSA) were as follows: (1) to assess the margin of safety of the reactor system design; (2) to calculate risk measures as a means of assessment of safety in terms of levels of risk to socity; (3) to identify the equipment, human actions, and plant design features that contribute in greatest measure to assurance of overall safety by exercising the analytical models that constitute the PSA.
- Research Organization:
- Westinghouse Savannah River Co., Aiken, SC (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- OSTI ID:
- 7073750
- Report Number(s):
- CONF-911107--
- Journal Information:
- Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 63; ISSN TANSA; ISSN 0003-018X
- Publisher:
- American Nuclear Society
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
98 NUCLEAR DISARMAMENT, SAFEGUARDS, AND PHYSICAL PROTECTION
ACCIDENTS
CHEMICAL REACTIONS
COMBUSTION
COOLING SYSTEMS
CORIUM
CRITICALITY
DISEASES
ELEMENTS
EMERGENCY PLANS
ENERGY TRANSFER
FLUID MECHANICS
FUEL-COOLANT INTERACTIONS
HAZARDS
HEALTH HAZARDS
HEAT TRANSFER
HEAVY WATER MODERATED REACTORS
HUMAN FACTORS
HYDRAULICS
HYDROGEN
IRRADIATION
K REACTOR
LETHAL IRRADIATION
MECHANICAL STRUCTURES
MECHANICS
MELTDOWN
MOLTEN METAL-WATER REACTIONS
NATIONAL ORGANIZATIONS
NEOPLASMS
NONMETALS
Nuclear Criticality Safety Program (NCSP)
OCCUPATIONAL EXPOSURE
OPERATION
OXIDATION
PRIMARY COOLANT CIRCUITS
PROBABILISTIC ESTIMATION
PRODUCTION REACTORS
Probabilistic Safety Assessment (PSA)
Probabilistic Study
RADIATION HAZARDS
RADIOACTIVITY TRANSPORT
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORE DISRUPTION
REACTOR OPERATION
REACTOR SAFETY
REACTORS
RISK ASSESSMENT
Results
Risk Assessment
SAFETY
SAVANNAH RIVER PLANT
SOURCE TERMS
SPECIAL PRODUCTION REACTORS
Special Materials Production Reactors
THERMOCHEMICAL PROCESSES
US AEC
US DOE
US ERDA
US ORGANIZATIONS