TS-1 and TS-2 transient overpower tests on FFTF fuel
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5592391
The TS-1 and TS-2 Transient Reactor Test Facility (TREAT) experiments were conducted on irradiated Fast Flux Test Facility (FFTF) fuel pins to characterize their failure behavior when subjected to hypothetical 5%/s transient overpower conditions. The TS-1 test employed a near-fresh (2 MWd/kg) fuel pin, while the TS-2 test used a medium-burnup (58 MWd/kg) fuel pin. Transient conditions were closely matched between the two experiments to provide a direct comparison of burnup effects on the failure response.
- Research Organization:
- Westinghouse Hanford Co., Richland, WA
- OSTI ID:
- 5592391
- Report Number(s):
- CONF-851115-
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 50
- Country of Publication:
- United States
- Language:
- English
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·
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
AIR COOLED REACTORS
BURNUP
DETECTION
ENRICHED URANIUM REACTORS
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FFTF REACTOR
FUEL ELEMENT FAILURE
FUEL ELEMENTS
FUEL MOTION DETECTION
FUEL PINS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HOMOGENEOUS REACTORS
IRRADIATION
LIQUID METAL COOLED REACTORS
POST-IRRADIATION EXAMINATION
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORES
REACTOR SAFETY
REACTOR SAFETY EXPERIMENTS
REACTOR SHUTDOWN
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SAFETY
SCRAM
SHUTDOWNS
SODIUM COOLED REACTORS
SOLID HOMOGENEOUS REACTORS
TEST REACTORS
THERMAL REACTORS
TRANSIENT OVERPOWER ACCIDENTS
TREAT REACTOR
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
AIR COOLED REACTORS
BURNUP
DETECTION
ENRICHED URANIUM REACTORS
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FFTF REACTOR
FUEL ELEMENT FAILURE
FUEL ELEMENTS
FUEL MOTION DETECTION
FUEL PINS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HOMOGENEOUS REACTORS
IRRADIATION
LIQUID METAL COOLED REACTORS
POST-IRRADIATION EXAMINATION
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORES
REACTOR SAFETY
REACTOR SAFETY EXPERIMENTS
REACTOR SHUTDOWN
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SAFETY
SCRAM
SHUTDOWNS
SODIUM COOLED REACTORS
SOLID HOMOGENEOUS REACTORS
TEST REACTORS
THERMAL REACTORS
TRANSIENT OVERPOWER ACCIDENTS
TREAT REACTOR