| α-U and ω-UZr2 in neutron irradiated U-10Zr annular metallic fuel T Yao, L Capriotti, JM Harp, X Liu, Y Wang, F Teng, DJ Murray, ... Journal of Nuclear Materials 542, 152536, 2020 | 34 | 2020 |
| Non-Destructive post-irradiation examination results of the first modern fueled experiments in TREAT J Schulthess, N Woolstenhulme, A Craft, J Kane, N Boulton, W Chuirazzi, ... Journal of Nuclear Materials 541, 152442, 2020 | 25 | 2020 |
| Microstructural characterization of as-cast U-20Pu-10Zr-3.86 Pd and U-20Pu-10Zr-3.86 Pd-4.3 Ln MT Benson, L He, JA King, RD Mariani, AJ Winston, JW Madden Journal of Nuclear Materials 508, 310-318, 2018 | 17 | 2018 |
| Investigation of fuel microstructure at the top of a metallic fuel pin after a reactor overpower transient FG Di Lemma, KE Wright, L Capriotti, AX Zabriskie, AJ Winston, ... Journal of Nuclear Materials 544, 152711, 2021 | 15 | 2021 |
| Characterization of solid fission products in 13.7% FIMA MOX fuel using electron microscopy techniques RJ Parrish, KE Wright, AJ Winston, C McKinney, JM Harp, A Aitkaliyeva Journal of Nuclear Materials 524, 67-79, 2019 | 14 | 2019 |
| Texture analyses and microstructural evolution in monolithic U-Mo nuclear fuel FG Di Lemma, J Burns, JW Madden, AJ Winston, AB Robinson, JF Jue, ... Journal of Nuclear Materials 544, 152677, 2021 | 13 | 2021 |
| Post-transient examination of performance of uranium silicide fuel and silicon-carbide composite cladding under reactivity-initiated accident conditions J Schulthess, D Kamerman, A Winston, A Pomo, T Trowbridge, X Pu, ... Journal of Nuclear Materials 560, 153520, 2022 | 12 | 2022 |
| Aluminum Spent Fuel Performance in Dry Storage Task 4 Aluminum Oxide Sampling of ATR Dry Stored Fuel PL Winston, S Middlemas, A Winston, J Burns, K Tolman, X Liu, J Aguiar Idaho National Lab.(INL), Idaho Falls, ID (United States), 2020 | 12 | 2020 |
| TEM characterization of high burnup fast-reactor MOX fuel R Parrish, A Winston, J Harp, A Aitkaliyeva Journal of Nuclear Materials 527, 151794, 2019 | 12 | 2019 |
| Radial microstructural evolution in low burnup fast reactor MOX fuel RJ Parrish, X Liu, A Winston, JM Harp, A Aitkaliyeva Journal of Nuclear Materials 523, 182-188, 2019 | 9 | 2019 |
| Best practices for preparing radioactive specimens for EBSD analysis T Ajantiwalay, T Trowbridge, A Winston, C Sun, K Sridharan, A Aitkaliyeva Micron 118, 1-8, 2019 | 9 | 2019 |
| 3D reconstructions of irradiated UMo fuel to understand breaching effects in ZrN diffusion barriers BD Miller, DD Keiser Jr, M Abir, A Aitkaliyeva, A Leenaers, BJ Hernandez, ... Journal of Nuclear Materials 510, 431-436, 2018 | 7 | 2018 |
| An investigation of the failure modes in U-10Mo monolithic fuel irradiated to high burnup C Smith, JF Jue, D Keiser, T Trowbridge, B Miller, A Robinson, A Winston, ... Journal of Nuclear Materials 575, 154202, 2023 | 5 | 2023 |
| Texture analyses and microstructural evolution in irradiated monolithic U-Mo nuclear fuel F Di Lemma, J Burns, A Winston, J Madden, JF Jue, D Keiser Microscopy and Microanalysis 26 (S2), 1116-1118, 2020 | 5 | 2020 |
| Impacts of annealing treatment on the microstructure of U-Mo monolithic fuel plates FG Di Lemma, JF Jue, AJ Winston, X Pu, S Anderson, DD Keiser, ... Journal of Nuclear Materials 564, 153687, 2022 | 4 | 2022 |
| Transmission electron microscopy investigation of phase transformation and fuel constituent redistribution in neutron irradiated U-10wt.% Zr fuel J Thomas, X Liu, L He, D Murray, F Teng, B Kombaiah, A Winston, ... Journal of Nuclear Materials 581, 154443, 2023 | 2 | 2023 |
| In-situ small-scale mechanical testing of fast reactor mixed oxide pins: completion report F Cappia, D Frazer, BD Miller, DJ Murray, AJ Winston, JM Harp Idaho National Lab.(INL), Idaho Falls, ID (United States), 2019 | 2 | 2019 |
| Contributions to the mechanistic understanding of the microstructural evolution in irradiated U-Mo dispersion fuel D Salvato, CA Smith, TR Pavlov, WA Hanson, KK Bawane, MN Bachhav, ... Journal of Nuclear Materials 588, 154789, 2024 | 1 | 2024 |
| Nanoindentation testing of high burn-up fast reactor mixed oxide fuel D Frazer, F Cappia, B Miller, D Murray, A Winston, A Pomo, JT White Journal of Nuclear Materials 564, 153668, 2022 | 1 | 2022 |
| Micro-tensile testing of the bond line in hot isostatic pressed aluminum D Frazer, F Teng, D Murray, A Pomo, A Winston, JI Cole, JF Jue, J Giglio Journal of Nuclear Materials 561, 153532, 2022 | 1 | 2022 |
