The use of PRA (Probabilistic Risk Assessment) in the management of safety issues at the High Flux Isotope Reactor
Conference
·
OSTI ID:6801858
The High Flux Isotope reactor (HFIR) is a high performance isotope production and research reactor which has been in operation at Oak Ridge National Laboratory (ORNL) since 1965. In late 1986 the reactor was shut down as a result of discovery of unexpected neutron embrittlement of the reactor vessel. In January of 1988, a level 1 Probabilistic Risk Assessment (PRA) (excluding external events) was published as part of the response to the many reviews that followed the shutdown and for use by ORNL to prioritize action items intended to upgrade the safety of the reactor. A conservative estimate of the core damage frequency initiated by internal events for HFIR was 3.11 {times} 10{sup {minus}4}. In June 1989 a draft external events initiated PRA was published. The dominant contributions from external events came from seismic, wind, and fires. The overall external event contribution to core damage frequency is about 138% of the internal event initiated contribution and is dominated by wind initiators. The PRA has provided a basis for the management of a wide range of safety and operation issues at the HFIR. 3 refs., 4 figs., 2 tabs.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- Sponsoring Organization:
- DOE/ER
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 6801858
- Report Number(s):
- CONF-900917-17; ON: DE91000724
- Country of Publication:
- United States
- Language:
- English
Similar Records
External event Probabilistic Risk Assessment for the High Flux Isotope Reactor (HFIR)
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Conference
·
Sat Dec 31 23:00:00 EST 1988
·
OSTI ID:5679452
Risk and safety analysis in support of the operation at the High Flux Isotope Reactor at Oak Ridge
Conference
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Sat Dec 31 23:00:00 EST 1988
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OSTI ID:5579697
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Journal Article
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· Nuclear Safety (Bimonthly Technical Progress Review); (United States)
·
OSTI ID:6148195
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
CONTAINERS
DISASTERS
EMBRITTLEMENT
ENRICHED URANIUM REACTORS
FIRES
FLOODS
HFIR REACTOR
IRRADIATION REACTORS
ISOTOPE PRODUCTION REACTORS
MANAGEMENT
REACTOR ACCIDENTS
REACTOR SAFETY
REACTOR VESSELS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
RISK ASSESSMENT
SAFETY
SEISMIC EFFECTS
TANK TYPE REACTORS
TEST REACTORS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
CONTAINERS
DISASTERS
EMBRITTLEMENT
ENRICHED URANIUM REACTORS
FIRES
FLOODS
HFIR REACTOR
IRRADIATION REACTORS
ISOTOPE PRODUCTION REACTORS
MANAGEMENT
REACTOR ACCIDENTS
REACTOR SAFETY
REACTOR VESSELS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
RISK ASSESSMENT
SAFETY
SEISMIC EFFECTS
TANK TYPE REACTORS
TEST REACTORS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS