N Reactor limited-scope probabilistic risk assessment
This document reports the results of a Limited-Scope Probabilistic Risk Assessment (PRA) of N Reactor operation. The study has a three-fold purpose: support the overall N Reactor Confinement Effectiveness Study intended to provide a basis for comparison between a standard nuclear plant with containment and the N Reactor with confinement; provide early and conservative estimates of radiological risk from operation of N Reactor, using the best information available currently to assist decision makers as they examine questions pertaining to continued N Reactor operation; and identify the accident sequences that are principal contributors to radiological risk so that resources for the current full-scope PRA can be focused on analysis of these sequences. 66 refs., 49 figs., 23 tabs.
- Research Organization:
- Westinghouse Hanford Co., Richland, WA (USA); Science Applications International Corp., Albuquerque, NM (USA)
- Sponsoring Organization:
- DOE/DP
- DOE Contract Number:
- AC06-87RL10930
- OSTI ID:
- 7048432
- Report Number(s):
- WHC-SP-0001; ON: DE90009493
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220502 -- Nuclear Reactor Technology-- Environmental Aspects-- Radioactive Effluents
220700 -- Nuclear Reactor Technology-- Plutonium & Isotope Production Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
AUXILIARY SYSTEMS
CONTAINMENT
CONTROL SYSTEMS
COOLING SYSTEMS
ENERGY SYSTEMS
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
FAILURE MODE ANALYSIS
FISSION PRODUCT RELEASE
FUEL ELEMENTS
GRAPHITE MODERATED REACTORS
HAZARDS
HEALTH HAZARDS
ISOTOPES
LWGR TYPE REACTORS
N-REACTOR
PLUTONIUM PRODUCTION REACTORS
POWER REACTORS
PRODUCTION REACTORS
RADIATION TRANSPORT
RADIOISOTOPES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CONTROL SYSTEMS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTORS
RISK ASSESSMENT
SAFETY
SHIELDING
SOURCE TERMS
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
WATER COOLED REACTORS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220502 -- Nuclear Reactor Technology-- Environmental Aspects-- Radioactive Effluents
220700 -- Nuclear Reactor Technology-- Plutonium & Isotope Production Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
AUXILIARY SYSTEMS
CONTAINMENT
CONTROL SYSTEMS
COOLING SYSTEMS
ENERGY SYSTEMS
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
FAILURE MODE ANALYSIS
FISSION PRODUCT RELEASE
FUEL ELEMENTS
GRAPHITE MODERATED REACTORS
HAZARDS
HEALTH HAZARDS
ISOTOPES
LWGR TYPE REACTORS
N-REACTOR
PLUTONIUM PRODUCTION REACTORS
POWER REACTORS
PRODUCTION REACTORS
RADIATION TRANSPORT
RADIOISOTOPES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CONTROL SYSTEMS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTORS
RISK ASSESSMENT
SAFETY
SHIELDING
SOURCE TERMS
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
WATER COOLED REACTORS