N reactor level 1 probabilistic risk assessment

Technical Report · Tue May 01 04:00:00 EDT 1990

DOI:https://doi.org/10.2172/6954643· OSTI ID:6954643

Zentner, M D; Atkinson, J K; Carlson, P A; Coles, G A; Leitz, E E; Lindberg, S E; Powers, T B ^[1]; Kelley, J E ^[2]

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1. Westinghouse Hanford Co., Richland, WA (USA)
2. Science Applications International Corp., San Diego, CA (USA)

It was recommended in 1982 that a Probabilistic Risk Assessment should be performed on the N Reactor. Thus, a three-level Probabilistic Risk Assessment study was initiated from this recommendation. This report documents work completed for the Level 1 Probabilistic Risk Assessment by describing the methodology used, the assumptions made, the analysis performed, and the final results. The four primary objectives that were fulfilled successfully by the Level 1 Probabilistic Risk Assessment included the following: identification of the plant features that are the most important contributors to the N Reactor fuel-damage frequency; development of plant logic models for use in analyzing safety and reliability issues; identification of dominant N Reactor accident sequences and their frequencies for input into the Level 2/3 Probabilistic Risk Assessment and external events analyses; and establishment of a Westinghouse Hanford company team with demonstrated expertise in performing risk and reliability analyses. 90 figs., 60 tabs.

• Research Organization: Westinghouse Hanford Co., Richland, WA (USA)
• Sponsoring Organization: DOE/DP
• DOE Contract Number: AC06-87RL10930
• OSTI ID: 6954643
• Report Number(s): WHC-EP-0322; ON: DE90012233
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220700 -- Nuclear Reactor Technology-- Plutonium & Isotope Production Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
AGING
AUXILIARY SYSTEMS
COOLING SYSTEMS
DOCUMENT TYPES
ECCS
ENERGY SYSTEMS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
FAILURE MODE ANALYSIS
FAILURES
FLUID MECHANICS
FUEL ELEMENT FAILURE
FUEL ELEMENTS
GRAPHITE MODERATED REACTORS
HEAT TRANSFER
HUMAN FACTORS
HYDRAULICS
LWGR TYPE REACTORS
MECHANICS
N-REACTOR
OPERATION
PLUTONIUM PRODUCTION REACTORS
POWER REACTORS
PRODUCTION REACTORS
PROGRESS REPORT
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR OPERATION
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
RELIABILITY
RISK ASSESSMENT
SAFETY
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
WATER COOLED REACTORS