Probabilistic risk assessment of the N Reactor using NUREG-1150 methods
A level-III probabilistic risk assessment (PRA) has been performed for N Reactor, a US Department of Energy (DOE) reactor located on the Hanford site in Washington state. The methods developed for the US Nuclear Regulatory Commission (NRC) by Sandia National Laboratories (SNL) in support of the NUREG-1150 effort were adapted for the analysis. The objectives of the study are to assess the risks to the public (off-site) and to workers at colocated DOE facilities (on-site) posed by the operation of N reactor, compare those risks to proposed DOE safety guidelines and NRC safety goals, and identify changes to the plant for safety enhancement. This summary is based on results from internally initiated events only. Off-site risk resulted from externally initiated events and on-site risk will be reported at a later date. The entire study is based on best-estimate inputs except that a number of areas, such as source term inventory and progression of metal/water reaction, apply conservative assumptions.
- OSTI ID:
- 6434162
- Report Number(s):
- CONF-891103--
- Journal Information:
- Transactions of the American Nuclear Society; (USA), Journal Name: Transactions of the American Nuclear Society; (USA) Vol. 60; ISSN TANSA; ISSN 0003-018X
- Country of Publication:
- United States
- Language:
- English
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N reactor level III probabilistic risk assessment using NUREG-1150 methods
Probabilistic risk assessment of N Reactor using NUREG-1150 methods
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22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ACCURACY
AFTER-HEAT REMOVAL
ATWS
CONTAINMENT
CONTAINMENT SYSTEMS
COOLING SYSTEMS
DOSES
ELEMENTS
ENERGY SYSTEMS
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
FISSION PRODUCT RELEASE
FISSION PRODUCTS
GRAPHITE MODERATED REACTORS
HANFORD RESERVATION
HAZARDS
HEALTH HAZARDS
HYDROGEN
ISOTOPES
LOSS OF COOLANT
LWGR TYPE REACTORS
MATERIALS
MITIGATION
MONTE CARLO METHOD
N-REACTOR
NATIONAL ORGANIZATIONS
NONMETALS
OPERATION
PLUTONIUM PRODUCTION REACTORS
POWER REACTORS
PRIMARY COOLANT CIRCUITS
PROBABILITY
PRODUCTION REACTORS
PUBLIC HEALTH
RADIATION DOSES
RADIATION HAZARDS
RADIOACTIVE MATERIALS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORE DISRUPTION
REACTOR OPERATION
REACTOR PROTECTION SYSTEMS
REACTOR SHUTDOWN
REACTORS
REMOVAL
RISK ASSESSMENT
SANDIA LABORATORIES
SCRAM
SHUTDOWN
SOURCE TERMS
TRANSIENTS
US AEC
US DOE
US ERDA
US NRC
US ORGANIZATIONS
WATER COOLED REACTORS