Fuel/cladding compatibility in high-burnup U-19 Pu-10 Zr/HT-9 clad fuel at elevated temperatures
- Argonne National Lab., IL (United States)
The U-Pu-Zr metallic fuel in the integral fast reactor may interact chemically with the steel cladding at elevated temperatures, leading to a thinning of the cladding and eventual pin failure. Also, as a result of the fuel/cladding chemical interaction (FCCI), iron may diffuse into the fuel and form a lower melting phase with uranium and plutonium. If the temperature is raised above the solidus temperature of this phase, the fuel can undergo liquefaction, i.e., the formation of a mixture of liquid and solid phases, that may promote further cladding interaction. Fuel/cladding chemical interaction, therefore, is a complex phenomenon on both sides of the fuel/cladding interface that depends on fuel and cladding compositions, linear power rating, burnup, and cladding temperature. The purpose of this study was to determine the temperature at which the fuel/cladding interaction region forms solid-plus-liquid phases above the normal in-reactor operating temperatures of high-burnup (11 at.%) Mark V-type fuel for the Experimental Breeder Reactor II (EBR-II). The Mark V fuel is being developed as a future driver fuel for the reactor. The effect of this solid-plus-liquid mixture on the kinetics and mechanism of FCCI was also investigated. This paper updates results previously reported for lower-burnup Mark V-type fuel elements.
- OSTI ID:
- 6982511
- Report Number(s):
- CONF-921102-; CODEN: TANSAO
- Journal Information:
- Transactions of the American Nuclear Society; (United States), Vol. 66; Conference: Joint American Nuclear Society (ANS)/European Nuclear Society (ENS) international meeting on fifty years of controlled nuclear chain reaction: past, present, and future, Chicago, IL (United States), 15-20 Nov 1992; ISSN 0003-018X
- Country of Publication:
- United States
- Language:
- English
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PERFORMANCE TESTING
PHASE STUDIES
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220600* - Nuclear Reactor Technology- Research
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