Thermal-hydraulic analysis of the HFIR (High Flux Isotope Reactor)
Conference
·
OSTI ID:6343738
- Oak Ridge National Lab., TN (USA)
- Oak Ridge Gaseous Diffusion Plant, TN (USA)
The High Flux Isotope Reactor (HFIR) at the Oak Ridge National Laboratory (ORNL) is a high performance research reactor used to produce transuranium isotopes and perform material irradiation studies. HFIR was operated for about 20 years prior to its shutdown in November 1986 and has remained shutdown while the results of safety studies are completed and reviewed. This paper highlights results from ongoing studies which have revisited system thermal-hydraulic safety limits with present day analytical tools and experimental investigations. Long term decay heat removal requirements have been examined as well as the response of the system to small break loss of coolant accidents (SBLOCA). 10 refs., 1 fig.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- Sponsoring Organization:
- DOE/ER
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 6343738
- Report Number(s):
- CONF-900608-43; ON: DE91004385
- 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
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220900* -- Nuclear Reactor Technology-- Reactor Safety
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
ACCIDENTS
AFTER-HEAT REMOVAL
COMPUTER CODES
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FLUID MECHANICS
HEAT TRANSFER
HFIR REACTOR
HYDRAULICS
IRRADIATION REACTORS
ISOTOPE PRODUCTION REACTORS
LOSS OF COOLANT
MECHANICS
R CODES
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
REMOVAL
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SAFETY
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
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
ACCIDENTS
AFTER-HEAT REMOVAL
COMPUTER CODES
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FLUID MECHANICS
HEAT TRANSFER
HFIR REACTOR
HYDRAULICS
IRRADIATION REACTORS
ISOTOPE PRODUCTION REACTORS
LOSS OF COOLANT
MECHANICS
R CODES
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
REMOVAL
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SAFETY
TANK TYPE REACTORS
TEST REACTORS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS