Cladding failure margins for metallic fuel in the integral fast reactor
Conference
·
OSTI ID:6303435
The reference fuel for Integral Fast Reactor (IFR) is a ternary U-Pu-Zr alloy with a low swelling austenitic or ferritic stainless steel cladding. It is known that low melting point eutectics may form in such metallic fuel-cladding systems which could contribute to cladding failure under accident conditions. This paper will present recent measurements of cladding eutectic penetration rates for the ternary IFR alloy and will compare these results with earlier eutectic penetration data for other fuel and cladding materials. A method for calculating failure of metallic fuel pins is developed by combining cladding deformation equations with a large strain analysis where the hoop stress is calculated using the instantaneous wall thickness as determined from correlations of the eutectic penetration-rate data. This method is applied to analyze the results of in-reactor and out-of-reactor fuel pin failure tests on uranium-fissium alloy EBR-II Mark-II driver fuel.
- Research Organization:
- Argonne National Lab., IL (USA)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 6303435
- Report Number(s):
- CONF-870812-22; ON: DE87011460
- 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
220300 -- Nuclear Reactor Technology-- Fuel Elements
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACTINIDE ALLOYS
ALLOYS
AUSTENITIC STEELS
BREEDER REACTORS
DATA
EBR-2 REACTOR
EPITHERMAL REACTORS
EUTECTICS
EXPERIMENTAL DATA
EXPERIMENTAL REACTORS
FAILURES
FAST REACTORS
FBR TYPE REACTORS
FUEL CANS
FUEL ELEMENTS
FUEL-CLADDING INTERACTIONS
IFR REACTOR
INFORMATION
IRON ALLOYS
IRON BASE ALLOYS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
NUMERICAL DATA
POWER REACTORS
REACTOR COMPONENTS
REACTOR SAFETY EXPERIMENTS
REACTORS
RESEARCH AND TEST REACTORS
SODIUM COOLED REACTORS
STEELS
THEORETICAL DATA
URANIUM ALLOYS
ZERO POWER REACTORS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220300 -- Nuclear Reactor Technology-- Fuel Elements
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACTINIDE ALLOYS
ALLOYS
AUSTENITIC STEELS
BREEDER REACTORS
DATA
EBR-2 REACTOR
EPITHERMAL REACTORS
EUTECTICS
EXPERIMENTAL DATA
EXPERIMENTAL REACTORS
FAILURES
FAST REACTORS
FBR TYPE REACTORS
FUEL CANS
FUEL ELEMENTS
FUEL-CLADDING INTERACTIONS
IFR REACTOR
INFORMATION
IRON ALLOYS
IRON BASE ALLOYS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
NUMERICAL DATA
POWER REACTORS
REACTOR COMPONENTS
REACTOR SAFETY EXPERIMENTS
REACTORS
RESEARCH AND TEST REACTORS
SODIUM COOLED REACTORS
STEELS
THEORETICAL DATA
URANIUM ALLOYS
ZERO POWER REACTORS