Extended overpower transient testing of oxide pins in EBR-II
Conference
·
OSTI ID:6947687
Understanding of the behavior of oxide fuel and blanket pins during slow transients with ramps between 0.1 and 10%/s is of importance because of the higher likelihood of such operational transient events. Compared to faster transients for which a fair amount of knowledge exists through testing in TREAT, there is also some concern of whether the oxide pins are particularly vulnerable to slower transients. For these reasons, a cooperative program between the US Department of Energy (DOE) and the Japanese Power Reactor and Nuclear Fuel Development Corporation (PNC) was launched to conduct operational transient testing (OTT) on oxide pins in EBR-II. A total of eleven tests is included in this OTT program. The status of the five extended-overpower-transient tests on preirradiated EBR-II pins is the subject of this paper.
- Research Organization:
- Argonne National Lab., IL (USA)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 6947687
- Report Number(s):
- CONF-830545-2; ON: DE84011743
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ACTINIDE COMPOUNDS
ALLOYS
BREEDER REACTORS
CHALCOGENIDES
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
EBR-2 REACTOR
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUEL CANS
FUEL ELEMENTS
FUEL PINS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
IRON ALLOYS
IRON BASE ALLOYS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MATERIALS
MOLYBDENUM ALLOYS
NICKEL ALLOYS
OXIDES
OXYGEN COMPOUNDS
PERFORMANCE TESTING
PLUTONIUM COMPOUNDS
PLUTONIUM DIOXIDE
PLUTONIUM OXIDES
POWER REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
SODIUM COOLED REACTORS
STAINLESS STEEL-316
STAINLESS STEELS
STEELS
STRESSES
TESTING
THERMAL STRESSES
TRANSIENT OVERPOWER ACCIDENTS
TRANSURANIUM COMPOUNDS
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ACTINIDE COMPOUNDS
ALLOYS
BREEDER REACTORS
CHALCOGENIDES
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
EBR-2 REACTOR
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUEL CANS
FUEL ELEMENTS
FUEL PINS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
IRON ALLOYS
IRON BASE ALLOYS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MATERIALS
MOLYBDENUM ALLOYS
NICKEL ALLOYS
OXIDES
OXYGEN COMPOUNDS
PERFORMANCE TESTING
PLUTONIUM COMPOUNDS
PLUTONIUM DIOXIDE
PLUTONIUM OXIDES
POWER REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
SODIUM COOLED REACTORS
STAINLESS STEEL-316
STAINLESS STEELS
STEELS
STRESSES
TESTING
THERMAL STRESSES
TRANSIENT OVERPOWER ACCIDENTS
TRANSURANIUM COMPOUNDS
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES