Design improvements to the high flux isotope reactor for safety enhancement
Journal Article
·
· Nuclear Safety (Bimonthly Technical Progress Review); (United States)
OSTI ID:6148195
- Oak Ridge National Lab., TN (United States)
The High Flux Isotope Reactor (HFIR) at the Oak Ridge National Laboratory (ORNL) was shut down in late 1986 for a reevaluation of the integrity of the pressure vessel because the radiation damage rate appeared to be greater than expected. The US Department of Energy (DOE) reviewed the reevaluation and a subsequent ORNL proposal for a 10-yr life extension of the vessel as well as the overall design and safety of the HFIR. In response to recommendations by the DOE-appointed review committees. ORNL performed a probabilistic risk assessment (PRA) to help identify and prioritize plant safety upgrades. Related studies performed before reactor restart included the internal-events PRA, the potential for and consequences of loss-of-coolant accidents (LOCAs), seismic upgrades, and decay heat removal. Ongoing programs to ensure that the level of safety continues to improve include an update of the internal-events PRA, an external-events PRA, additional LOCA studies, and implementation of an environmental qualification program. HFIR was restarted in April 1989 and is expected to be operational for an additional 10 effective full-power years.
- OSTI ID:
- 6148195
- Journal Information:
- Nuclear Safety (Bimonthly Technical Progress Review); (United States), Journal Name: Nuclear Safety (Bimonthly Technical Progress Review); (United States) Vol. 31:4; ISSN 0029-5604; ISSN NUSAA
- 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
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
AFTER-HEAT REMOVAL
CONTAINERS
CUMULATIVE RADIATION EFFECTS
EMBRITTLEMENT
ENGINEERING
ENRICHED URANIUM REACTORS
HFIR REACTOR
IRRADIATION REACTORS
ISOTOPE PRODUCTION REACTORS
LOSS OF COOLANT
NATIONAL ORGANIZATIONS
ORNL
PRESSURE VESSELS
RADIATION EFFECTS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
REMOVAL
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
RETROFITTING
RISK ASSESSMENT
SAFETY
SAFETY ENGINEERING
SERVICE LIFE
TANK TYPE REACTORS
TEST REACTORS
THERMAL REACTORS
US AEC
US DOE
US ERDA
US ORGANIZATIONS
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
AFTER-HEAT REMOVAL
CONTAINERS
CUMULATIVE RADIATION EFFECTS
EMBRITTLEMENT
ENGINEERING
ENRICHED URANIUM REACTORS
HFIR REACTOR
IRRADIATION REACTORS
ISOTOPE PRODUCTION REACTORS
LOSS OF COOLANT
NATIONAL ORGANIZATIONS
ORNL
PRESSURE VESSELS
RADIATION EFFECTS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
REMOVAL
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
RETROFITTING
RISK ASSESSMENT
SAFETY
SAFETY ENGINEERING
SERVICE LIFE
TANK TYPE REACTORS
TEST REACTORS
THERMAL REACTORS
US AEC
US DOE
US ERDA
US ORGANIZATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS