Seven pin bundle fast top tests L01 and L02. [LMFBR]
Conference
·
OSTI ID:6202651
Tests L01 and L02 were the first two seven pin bundle tests in the PFR/TREAT program of fuel failure tests carried out jointly by the US and the UK. The two tests were on bottom plenum annular pellet mixed oxide fuel clad in 316 stainless steel. L01 used fresh fuel, while L02 used PFR irradiated 4% burn-up fuel, to determine any differences in the failure mechanism and subsequent fuel behavior due to irradiation. They were performed in flowing sodium in the Mark IIIA version of a TREAT integral loop. Both were fast transient overpower (TOP) tests intended to simulate 5 $/s reactivity ramp hypothetical accidents in a large fast reactor. The test objectives were to obtain information on fuel motion in the central hole before failure, the time and location of cladding failures, and material motion in the channel after failure, having particular regard to the effect of irradiation.
- Research Organization:
- Argonne National Lab., IL (USA); UKAEA Atomic Energy Establishment, Winfrith; UKAEA Atomic Energy Research Establishment, Harwell
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 6202651
- Report Number(s):
- CONF-841105-12; ON: DE84014752
- Country of Publication:
- United States
- Language:
- English
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Slow transient overpower tests - C04, C05 and L03. [LMFBR]
Conference
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Sat Dec 31 23:00:00 EST 1983
·
OSTI ID:6339047
In-pile TREAT Test L04: simulating a lead sub-assembly in an unprotected LMFBR loss-of-coolant accident
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OSTI ID:5701417
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OSTI ID:6020034
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
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLOW RATE
FLUID MECHANICS
FUEL ASSEMBLIES
FUEL CANS
FUEL ELEMENT FAILURE
FUEL ELEMENTS
FUEL PINS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
HYDRAULICS
IRON ALLOYS
IRON BASE ALLOYS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MATERIALS
MECHANICS
MOLYBDENUM ALLOYS
NICKEL ALLOYS
OXIDES
OXYGEN COMPOUNDS
PERFORMANCE TESTING
PLUTONIUM COMPOUNDS
PLUTONIUM DIOXIDE
PLUTONIUM OXIDES
PRESSURE GRADIENTS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
SAFETY
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
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLOW RATE
FLUID MECHANICS
FUEL ASSEMBLIES
FUEL CANS
FUEL ELEMENT FAILURE
FUEL ELEMENTS
FUEL PINS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
HYDRAULICS
IRON ALLOYS
IRON BASE ALLOYS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MATERIALS
MECHANICS
MOLYBDENUM ALLOYS
NICKEL ALLOYS
OXIDES
OXYGEN COMPOUNDS
PERFORMANCE TESTING
PLUTONIUM COMPOUNDS
PLUTONIUM DIOXIDE
PLUTONIUM OXIDES
PRESSURE GRADIENTS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
SAFETY
STAINLESS STEEL-316
STAINLESS STEELS
STEELS
STRESSES
TESTING
THERMAL STRESSES
TRANSIENT OVERPOWER ACCIDENTS
TRANSURANIUM COMPOUNDS
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES