Possible impacts of Mo chemical banding and second phase impurities on the irradiation behavior of monolithic U-10Mo fuels

Smith, Charlyne A.; Jue, Jan-Fong; Trowbridge, Tammy; Keiser, Dennis; Madden, James; Robinson, Adam; Giglio, Jeffrey

doi:10.1016/j.jnucmat.2023.154264

Possible impacts of Mo chemical banding and second phase impurities on the irradiation behavior of monolithic U-10Mo fuels

Journal Article · Wed Jan 11 23:00:00 EST 2023 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2023.154264· OSTI ID:2309748

^[1]; Jue, Jan-Fong ^[1]; ^[1]; ^[1]; Madden, James ^[1]; ^[1]; Giglio, Jeffrey ^[1]

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

This study investigated the microstructural behavior of both full-size and mini-size monolithic U-10Mo fuel plates irradiated to high burnup with a focus on the evolution of the second phase impurities in monolithic U-Mo using scanning electron microscopy (SEM), energy dispersive spectroscopy (EDS), and wavelength dispersive spectroscopy (WDS). Key indicators of possible mechanical and thermal compromise include cracks, large fission gas porosity, and interconnection of fission gas pores. For the fission densities evaluated in this work (3.5 × 10²¹ fissions/cm³ -5.1 × 10²¹ fissions/cm³), fine porosity can develop along the UC phase boundary; however, the size of the fission gas pores is no more than those observed in the U-Mo fuel phase. Further, other inclusions such as Si-rich second-phase impurities found in the as-fabricated microstructure were difficult to resolve post-irradiation because they can become overshadowed by porosity development in the fuel phase. Additionally, the presence of a Fe-rich sublayer formed in the Zr diffusion layer during fabrication remained enriched in the Zr layer in the irradiated U-10Mo microstructures near the U-Mo/Zr interface; however, based on the burnup assessed in this study the identified impurities did not appear to contribute to notable microstructural degradation.

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:: 2309748

Report Number(s):: INL/JOU--23-74047-Rev000

Journal Information:: Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Vol. 576; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
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