JOURNAL OF NUCLEAR MATERIALS | 卷:539 |
Thermal conductivity measurement of the interaction layer between UMo and Al produced by high-energy heavy ion irradiation | |
Article | |
Miao, Yinbin1  Nimmagadda, Lakshmi Amulya2  Rajagopal, Manjunath C.2  Mo, Kun1  Shi, Jingyi3  Ye, Bei1  Jamison, Laura1  Kim, Yeon Soo1  Petry, Winfried3  Sinha, Sanjiv2,4  Yacout, Abdellatif M.1  | |
[1] Argonne Natl Lab, Lemont, IL 60439 USA | |
[2] Univ Illinois, Mech Sci & Engn Dept, Urbana, IL 61801 USA | |
[3] Tech Univ Munich, D-80333 Munich, Germany | |
[4] Univ Illinois, Micro & Nanotechnol Lab, Urbana, IL 61801 USA | |
关键词: High-energy ion irradiation; Thermal conductivity; Interaction layer; UMo fuel; Research reactors; | |
DOI : 10.1016/j.jnucmat.2020.152262 | |
来源: Elsevier | |
【 摘 要 】
Here, we report the first direct thermal conductivity measurement results for Al-UMo interaction layer (IL), which is typically observed in UMo/Al dispersion fuel plates under irradiation. The investigated IL was formed by irradiating Al coated UMo substrate using 80 MeV iodine ions at 180 degrees C up to 3.03 x 10(17) ions/cm(2) fluence. Microstructural characterization indicated that the induced IL is amorphous with an approximately (U-0.8,Mo-0.2)Al-5.3 stoichiometry, which is similar to that formed under in-pile irradiation. Focused ion beam (FIB) was used to prepare nine specimens of various lengths from the IL that could be suspended across a microfabricated device for thermal conductivity measurement. The measured thermal conductivity values of the IL were significantly lower than the values for both the original UMo fuel and the Al. The successful measurement of the Al-UMo IL provides valuable information for the development and qualification of UMo/Al dispersion fuels for research and test reactor conversion applications, and further demonstrates the promising capabilities of utilizing the suspended bridge method in nuclear fuel research. (C) 2020 Elsevier B.V. All rights reserved.
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