@article{dad82895836b459aa6fc73d2d89f1989,
title = "Micro-tensile testing of the bond line in hot isostatic pressed aluminum",
abstract = "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. 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.",
keywords = "Hot isostatic pressing, Micro-tensile testing, Post irradiation examination",
author = "D. Frazer and F. Teng and D. Murray and A. Pomo and A. Winston and Cole, \{J. I.\} and Jue, \{J. F.\} and J. Giglio",
note = "Funding Information: This submitted manuscript was authored by a contractor of the U.S. Government under DOE Contract No. DE-AC07–05ID14517. Accordingly, the U.S. Government retains and the publisher, by accepting the article for publication, acknowledges that the U.S. Government retains a nonexclusive, paid-up, irrevocable, world-wide license to publish or reproduce the published form of this manuscript, or allow others to do so, for U.S. Government purposes. The funding for this work was provided by the USHPRR Project, Office of Material Management and Minimization National Nuclear Security Administration from the U.S. Department of Energy under DOE-NE Idaho Operations Office Contract DE-AC07-05ID14517. Authors would like to acknowledg the staff of the Electron Microscopy Laboratory (EML) at the Materials and Fuels Complex (MFC) at Idaho National Laboratory for their effort in handling, preparing, and transferring of the specimens used in this work. The authors would like to thank Dr. Alissa Murray for a through proofreading of the manuscript. Funding Information: This submitted manuscript was authored by a contractor of the U.S. Government under DOE Contract No. DE-AC07–05ID14517. Accordingly, the U.S. Government retains and the publisher, by accepting the article for publication, acknowledges that the U.S. Government retains a nonexclusive, paid-up, irrevocable, world-wide license to publish or reproduce the published form of this manuscript, or allow others to do so, for U.S. Government purposes. The funding for this work was provided by the USHPRR Project, Office of Material Management and Minimization National Nuclear Security Administration from the U.S. Department of Energy under DOE-NE Idaho Operations Office Contract DE-AC07-05ID14517. Authors would like to acknowledg the staff of the Electron Microscopy Laboratory (EML) at the Materials and Fuels Complex (MFC) at Idaho National Laboratory for their effort in handling, preparing, and transferring of the specimens used in this work. The authors would like to thank Dr. Alissa Murray for a through proofreading of the manuscript. Publisher Copyright: {\textcopyright} 2022",
year = "2022",
month = apr,
day = "1",
doi = "10.1016/j.jnucmat.2022.153532",
language = "English",
volume = "561",
journal = "Journal of Nuclear Materials",
issn = "0022-3115",
publisher = "Elsevier B.V.",
}