Mechanical and Thermophysical properties of low enriched uranium-10wt% molybdenum rolled foils

Schulthess, Jason; Heighes, Michael; Michelich, Connor; Adkins, Cynthia; Marshall, M. Craig; Plummer, Mitchell; Lemma, Fidelma Di; Trowbridge, Tammy; Cole, James I.

doi:10.1016/j.jnucmat.2022.153628

Title: Mechanical and Thermophysical properties of low enriched uranium-10wt% molybdenum rolled foils

Journal Article · 25 February 2022 · Journal of Nuclear Materials

DOI: https://doi.org/10.1016/j.jnucmat.2022.153628 · OSTI ID:2349338

^[1]; Heighes, Michael ^[1]; Michelich, Connor ^[1]; Adkins, Cynthia ^[1];

^[1]; Plummer, Mitchell ^[1];

^[1]; Trowbridge, Tammy ^[1];

^[1]

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

In this study, low-enriched (~19.75% ²³⁵U) U-10Mo(wt%) foils were evaluated for both mechanical and thermophysical properties to establish baseline characteristics prior to irradiation testing. Cast U-10Mo ingots were sequentially hot and cold rolled to two different final foil thicknesses, resulting in different levels of cold work being present in the finished foils. The mechanical response of the U-10Mo foils was evaluated in the temperature range of 293–623 K. Increasing test temperatures resulted in decreases of both yield and ultimate tensile strength. Comparison of results to earlier work performed on depleted U-10Mo rolled foils indicates that the material in this study has lower strength and increased ductility. However, a comparison of the two different foil thicknesses in this study found that they were nearly identical in yield and ultimate tensile strength, differing by only 10–20 MPa (<2%). Thermal conductivity was calculated from the measurements of specific heat, linear thermal expansion, and thermal diffusivity from 323 to 1273 K on both thicknesses of the foils. These data were approximately 5–10% lower than previously published data above 573 K and were similar to data for temperature ranges below 573 K. Differences are likely related to differences in grain size and/or impurity content and variation in fabrication history.

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

Sponsoring Organization:: USDOE

Grant/Contract Number:: AC07-05ID14517

OSTI ID:: 2349338

Report Number(s):: INL/JOU-20-57965-Rev000

Journal Information:: Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Vol. 563; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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