Micro-tensile testing of the bond line in hot isostatic pressed aluminum

Frazer, David M.; Teng, Fei; Murray, Daniel J.; Pomo, Alex N.; Winston, Alexander J.; Cole, James I.; Jue, Jan-Fong; Giglio, Jeffrey J.

doi:10.1016/j.jnucmat.2022.153532

Title: Micro-tensile testing of the bond line in hot isostatic pressed aluminum

Journal Article · 11 January 2022 · Journal of Nuclear Materials

DOI: https://doi.org/10.1016/j.jnucmat.2022.153532 · OSTI ID:1905189

Frazer, David M. ^[1];

^[1];

^[1]; Pomo, Alex N. ^[1];

^[1];

^[1]

Idaho National Lab. (INL), Idaho Falls, ID (United States)

Considerable effort is being devoted to development and regulatory qualification of low enriched fuels for research and test reactors by many agencies worldwide. One promising fuel configuration being examined for United States higher power research and test reactors (USHPRRs) are plate-type fuels composed of a metallic uranium-molybdenum foil clad in an aluminum alloy. The two pieces of aluminum alloy cladding are bonded using a hot isostatic pressing method. The mechanical properties of the resulting bond line in the aluminum alloy cladding will vary by the HIP'ing parameters, requiring a need to characterize the bond line. Small scale mechanical testing can provide a path for evaluating the mechanical properties and deformation behavior of the bond line both prior to and following irradiation. Here, in this research, room temperature micro-tensile specimens of non-irradiated and irradiated samples containing an Al alloy (AA 6061) bond line were tested to evaluate its strength and deformation behavior. Observations indicated that the strain rate did not affect the deformation behavior or strength and most of the micro-tensile specimens failed in a ductile mode in grains around the bond line. There was no indication that the microstructural features from the bond line affected the mechanical properties of the micro-tensile specimens. An initial examination was performed on irradiated material but further systematic studies of the effects of irradiation can be performed in the future.

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

Sponsoring Organization:: USDOE Office of Nuclear Energy (NE)

Grant/Contract Number:: AC07-05ID14517

OSTI ID:: 1905189

Report Number(s):: INL/JOU-21-64779-Rev000

Journal Information:: Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Vol. 561; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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