Accident progression event tree analysis for postulated severe accidents at N Reactor
- Sandia National Labs., Albuquerque, NM (USA)
- Science Applications International Corp., Albuquerque, NM (USA)
A Level II/III probabilistic risk assessment (PRA) has been performed for N Reactor, a Department of Energy (DOE) production reactor located on the Hanford reservation in Washington. The accident progression analysis documented in this report determines how core damage accidents identified in the Level I PRA progress from fuel damage to confinement response and potential releases the environment. The objectives of the study are to generate accident progression data for the Level II/III PRA source term model and to identify changes that could improve plant response under accident conditions. The scope of the analysis is comprehensive, excluding only sabotage and operator errors of commission. State-of-the-art methodology is employed based largely on the methods developed by Sandia for the US Nuclear Regulatory Commission in support of the NUREG-1150 study. The accident progression model allows complex interactions and dependencies between systems to be explicitly considered. Latin Hypecube sampling was used to assess the phenomenological and systemic uncertainties associated with the primary and confinement system responses to the core damage accident. The results of the analysis show that the N Reactor confinement concept provides significant radiological protection for most of the accident progression pathways studied.
- Research Organization:
- Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
- Sponsoring Organization:
- DOE/EH
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 6767616
- Report Number(s):
- SAND-89-2100; ON: DE90013558; TRN: 90-028880
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
N-REACTOR
FAILURE MODE ANALYSIS
RISK ASSESSMENT
BOUNDARY CONDITIONS
CONTAINMENT
FUEL ELEMENTS
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
REACTOR COOLING SYSTEMS
REACTOR SAFETY
SOURCE TERMS
SYSTEMS ANALYSIS
ACCIDENTS
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FLUID MECHANICS
GRAPHITE MODERATED REACTORS
LWGR TYPE REACTORS
MECHANICS
PLUTONIUM PRODUCTION REACTORS
POWER REACTORS
PRODUCTION REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
SAFETY
SYSTEM FAILURE ANALYSIS
WATER COOLED REACTORS
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