Abstract
This article reports the results and interpretation of post-irradiation non-destructive examinations performed on four curved full-size fuel plates that comprise the AFIP-7 experiment. These fuel plates, having a U-10 wt.%Mo monolithic design, were irradiated under moderate operating conditions in the Advanced Test Reactor to assess fuel performance for geometries that are prototypic of research reactor fuel assemblies. Non-destructive examinations include visual examination, neutron radiography, profilometry, and precision gamma scanning. This article evaluates the qualitative and quantitative data taken for each plate, compares corresponding data sets, and presents the results of swelling analyses. These characterization results demonstrate that the fuel meets established irradiation performance requirements for mechanical integrity, geometric stability, and stable and predictable behavior.
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Funding was provided by Materials Management and Minimization (M3).
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Williams, W.J., Robinson, A.B. & Rabin, B.H. Post-Irradiation Non-Destructive Analyses of the AFIP-7 Experiment. JOM 69, 2546–2553 (2017). https://doi.org/10.1007/s11837-017-2552-y
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DOI: https://doi.org/10.1007/s11837-017-2552-y