| Transmission electron microscopy characterization of irradiated U–7Mo/Al–2Si dispersion fuel J Gan, DD Keiser Jr, DM Wachs, AB Robinson, BD Miller, TR Allen Journal of Nuclear Materials 396 (2-3), 234-239, 2010 | 133 | 2010 |
| Fuel-cladding chemical interaction in U-Pu-Zr metallic fuels: A critical review C Matthews, C Unal, J Galloway, DD Keiser Jr, SL Hayes Nuclear Technology 198 (3), 231-259, 2017 | 98 | 2017 |
| High-density, low-enriched uranium fuel for nuclear research reactors DD Keiser Jr, SL Hayes, MK Meyer, CR Clark Jom 55 (9), 55-58, 2003 | 98 | 2003 |
| Microstructural development in irradiated U-7Mo/6061 Al alloy matrix dispersion fuel DD Keiser Jr, AB Robinson, JF Jue, P Medvedev, DM Wachs, MR Finlay Journal of Nuclear Materials 393 (2), 311-320, 2009 | 87 | 2009 |
| Fabrication of monolithic RERTR fuels by Hot Isostatic Pressing JF Jue, BH Park, CR Clark, GA Moore, DD Keiser Jr Nuclear technology 172 (2), 204-210, 2010 | 84 | 2010 |
| TEM characterization of U–7Mo/Al–2Si dispersion fuel irradiated to intermediate and high fission densities J Gan, DD Keiser Jr, BD Miller, AB Robinson, JF Jue, P Medvedev, ... Journal of nuclear materials 424 (1-3), 43-50, 2012 | 78 | 2012 |
| Interdiffusion behavior in U Pu Zr fuel versus stainless steel couples DD Keiser Jr, MC Petri Journal of nuclear materials 240 (1), 51-61, 1996 | 75 | 1996 |
| Microstructural analysis of as-processed U–10 wt.% Mo monolithic fuel plate in AA6061 matrix with Zr diffusion barrier E Perez, B Yao, DD Keiser Jr, YH Sohn Journal of Nuclear Materials 402 (1), 8-14, 2010 | 74 | 2010 |
| Interdiffusion between U-Zr fuel and selected Fe-Ni-Cr alloys DD Keiser Jr, MA Dayananda Journal of Nuclear materials 200 (2), 229-243, 1993 | 67 | 1993 |
| Swelling of U (Mo)–Al (Si) dispersion fuel under irradiation–Non-destructive analyses of the LEONIDAS E-FUTURE plates S Van den Berghe, Y Parthoens, F Charollais, YS Kim, A Leenaers, ... Journal of nuclear materials 430 (1-3), 246-258, 2012 | 66 | 2012 |
| Microstructural characteristics of HIP-bonded monolithic nuclear fuels with a diffusion barrier JF Jue, DD Keiser Jr, CR Breckenridge, GA Moore, MK Meyer Journal of Nuclear Materials 448 (1-3), 250-258, 2014 | 58 | 2014 |
| Influence of technetium on the microstructure of a stainless steel–zirconium alloy DD Keiser Jr, DP Abraham, JW Richardson Jr Journal of nuclear materials 277 (2-3), 333-338, 2000 | 57 | 2000 |
| Advantages and disadvantages of using a focused ion beam to prepare TEM samples from irradiated U–10Mo monolithic nuclear fuel BD Miller, J Gan, J Madden, JF Jue, A Robinson, DD Keiser Jr Journal of Nuclear Materials 424 (1-3), 38-42, 2012 | 55 | 2012 |
| Transmission electron microscopy characterization of the fission gas bubble superlattice in irradiated U–7 wt% Mo dispersion fuels BD Miller, J Gan, DD Keiser Jr, AB Robinson, JF Jue, JW Madden, ... Journal of Nuclear Materials 458, 115-121, 2015 | 52 | 2015 |
| Irradiation performance of u-mo alloy based ‘monolithic’plate-type fuel–design selection AB Robinson, GS Chang, DD Keiser Jr, DM Wachs, DL Porter Idaho National Lab.(INL), Idaho Falls, ID (United States), 2009 | 52 | 2009 |
| Actinide distribution in a stainless steel–15 wt% zirconium high-level nuclear waste form DD Keiser Jr, DP Abraham, W Sinkler, JW Richardson Jr, SM McDeavitt Journal of nuclear materials 279 (2-3), 234-244, 2000 | 46 | 2000 |
| Irradiated microstructure of U-10Mo monolithic fuel plate at very high fission density J Gan, BD Miller, DD Keiser Jr, JF Jue, JW Madden, AB Robinson, ... Journal of Nuclear Materials 492, 195-203, 2017 | 41 | 2017 |
| 3.15-metal fuel-cladding interaction DD Keiser Comprehensive Nuclear Materials: Volume 1-5, 423-441, 2012 | 39 | 2012 |
| Effects of irradiation on the microstructure of U–7Mo dispersion fuel with Al–2Si matrix DD Keiser Jr, JF Jue, AB Robinson, P Medvedev, J Gan, BD Miller, ... Journal of nuclear materials 425 (1-3), 156-172, 2012 | 37 | 2012 |
| Microstructural characterization of U–7Mo/Al–Si alloy matrix dispersion fuel plates fabricated at 500 C DD Keiser Jr, JF Jue, B Yao, E Perez, Y Sohn, CR Clark Journal of Nuclear Materials 412 (1), 90-99, 2011 | 36 | 2011 |
