Evaluating the Effects of Hydride Embrittlement and Pulse Width on Zircaloy Cladding Transient Performance
Conference
·
OSTI ID:1974775
- Idaho National Laboratory
Pellet Cladding Mechanical Interaction is the primary failure mode for high burnup Zircaloy claddings in Light Water Reactor Reactivity Initiated Accidents. This failure mode is not seen in fresh and lower burnup fuels and is the result of environmental degradation of the cladding material and the unique loading condition on the cladding as a result of the sudden contact forces with the pellet. This paper describes work that is underway at the Idaho National Laboratory to better understand this failure mode by pre-hydriding fresh Zircaloy cladding. The pre-hydrided cladding is being mechanically characterized and will ultimately be used as part of an in-pile testing campaign at the TREAT reactor that will simulate the unique transient loading and heating conditions present in a Reactivity Initiated Accident. A description of the pre-hydriding and mechanical testing processes being followed, and initial results are presented followed by a description of the planned transient testing
- Research Organization:
- Idaho National Laboratory (INL), Idaho Falls, ID (United States)
- Sponsoring Organization:
- USDOE Office of Nuclear Energy (NE), Fuel Cycle Technologies (NE-5)
- DOE Contract Number:
- AC07-05ID14517
- OSTI ID:
- 1974775
- Report Number(s):
- INL/CON-19-53315-Rev000
- Country of Publication:
- United States
- Language:
- English
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