Application of phenomenological calculations to the N Reactor probabilistic risk assessment
Conference
·
OSTI ID:6732745
A deterministic phenomenological calculation generates only a single best estimate result. However, probabilistic risk assessment (PRA) accident progression calculations require phenomenological data in the form of probability distributions. A three step process, to provide such distributions, consisting of issue identification, deterministic calculation specification, and the use of expert judgment to interpret the results, is described in this paper. The results of a sample expert judgment elicitation from the N Reactor PRA are included to demonstrate how the uncertainties associated with deterministic calculations are accounted for in the final probability distributions that are based on those calculations. 6 refs., 2 figs., 3 tabs.
- Research Organization:
- Sandia National Labs., Albuquerque, NM (USA)
- Sponsoring Organization:
- DOE/DP
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 6732745
- Report Number(s):
- SAND-90-0113C; CONF-900917--11; ON: DE90015166
- 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
220700 -- Nuclear Reactor Technology-- Plutonium & Isotope Production Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
ACCIDENTS
CHEMICAL REACTIONS
COMPUTER CODES
CONTAINMENT
COOLING SYSTEMS
ECCS
ELEMENTS
ENERGY SYSTEMS
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
FUEL ELEMENTS
GRAPHITE MODERATED REACTORS
H CODES
HYDROGEN
LWGR TYPE REACTORS
M CODES
N-REACTOR
NONMETALS
PLUTONIUM PRODUCTION REACTORS
POWER REACTORS
PROBABILITY
PRODUCTION REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORES
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
RISK ASSESSMENT
SAFETY
WATER COOLED REACTORS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220700 -- Nuclear Reactor Technology-- Plutonium & Isotope Production Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
ACCIDENTS
CHEMICAL REACTIONS
COMPUTER CODES
CONTAINMENT
COOLING SYSTEMS
ECCS
ELEMENTS
ENERGY SYSTEMS
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
FUEL ELEMENTS
GRAPHITE MODERATED REACTORS
H CODES
HYDROGEN
LWGR TYPE REACTORS
M CODES
N-REACTOR
NONMETALS
PLUTONIUM PRODUCTION REACTORS
POWER REACTORS
PROBABILITY
PRODUCTION REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORES
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
RISK ASSESSMENT
SAFETY
WATER COOLED REACTORS