An investigation of the failure modes in U-10Mo monolithic fuel irradiated to high burnup

Smith, Charlyne A.; Jue, Jan-Fong; Keiser Jr., Dennis D.; Trowbridge, Tammy L.; Miller, Brandon D.; Robinson, Adam B.; Winston, Alexander; Giglio, Jeffery

doi:10.1016/j.jnucmat.2022.154202

An investigation of the failure modes in U-10Mo monolithic fuel irradiated to high burnup

Journal Article · Thu Dec 15 00:00:00 EST 2022 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2022.154202· OSTI ID:1957642

Smith, Charlyne A. ^[1]; ^[1]; ^[1]; Trowbridge, Tammy L. ^[1]; Miller, Brandon D. ^[1]; Robinson, Adam B. ^[1]; Winston, Alexander ^[1]; Giglio, Jeffery ^[1]

Idaho National Laboratory (INL), Idaho Falls, ID (United States)

Here, this study investigated possible failure mode sequences in U-10Mo monolithic fuel irradiated to very-high-burnup. The U-Mo fuel plate used in this study was characterized using scanning electron microscopy (SEM), wavelength dispersive spectroscopy (WDS), and image analysis techniques to investigate how microstructural features may initiate crack formation and propagation through the microstructure, potentially leading to blistering. Distinctly large fission gas pores (FGPs) were observed to preferentially align 5-15µm away from the U-10Mo/Zr interface, parallel to the Zr diffusion barrier. Preferential growth, alignment, and interconnection of FGP could initiate blistering in the fuel plate by creating a fission gas channel, parallel to the U-Mo/Zr interface. FGP alignment in the fuel phase near the U-Mo/Zr interface is believed to be one of the precursors to crack and Type 2 blister formation in monolithic U-Mo fuels. The chemical maps revealed differences in fission product behavior near the U-Mo/Zr interface such that Nd remains in the fuel matrix at the FGP sites. On the other hand, other fission products like Xe and Cs can get trapped in FGPs by Nd in the fuel phase and/or diffuse toward the Zr diffusion barrier.

View Accepted Manuscript (DOE)

Research Organization:: Idaho National Laboratory (INL), Idaho Falls, ID (United States)

Sponsoring Organization:: USDOE National Nuclear Security Administration (NNSA)

Grant/Contract Number:: AC07-05ID14517

OSTI ID:: 1957642

Report Number(s):: INL/JOU-22-66978

Journal Information:: Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Journal Issue: - Vol. 575; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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An investigation of the failure modes in U-10Mo monolithic fuel irradiated to high burnup

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