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Advanced Characterization of Fuel Cladding Chemical Interaction between U-10Zr Fuel and HT9 Cladding Tested in Fast Flux Test Facility

Published online by Cambridge University Press:  22 July 2022

Yachun Wang*
Affiliation:
Idaho National Laboratory, Idaho Falls, ID, USA
Brandon D. Miller
Affiliation:
Idaho National Laboratory, Idaho Falls, ID, USA
Jason M. Harp
Affiliation:
Idaho National Laboratory, Idaho Falls, ID, USA Currently at Oak Ridge National Laboratory
Mukesh N. Bachhav
Affiliation:
Idaho National Laboratory, Idaho Falls, ID, USA
Luca Capriotti
Affiliation:
Idaho National Laboratory, Idaho Falls, ID, USA
Tiankai Yao
Affiliation:
Idaho National Laboratory, Idaho Falls, ID, USA
*
*Corresponding author: yachun.wang@inl.gov

Abstract

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Type
Correlative Microscopy and High-Throughput Characterization for Accelerated Development of Materials in Extreme Environments
Copyright
Copyright © Microscopy Society of America 2022

References

Carmack, WJ, Idaho National Laboratory (INL) (2012).Google Scholar
Porter, D and Crawford, D, Nuclear Science and Engineering (2022). p. 1.Google Scholar
Harp, JM et al. , Journal of Nuclear Materials 494 (2017), p. 227.10.1016/j.jnucmat.2017.07.040CrossRefGoogle Scholar
Work supported through a INL Laboratory Directed Research& Development (LDRD, project 22A1059-094FP) and a Nuclear Science User Facilities Rapid Turnaround Experiment Proposal (NSUF-RTE, FY-2021 1st call, #4345) programs under DOE Idaho Operations Office Contract DE-AC07-05ID14517. We also acknowledge the partial support from US Department of Energy Advanced Fuel Campaign (AFC) Program.Google Scholar