| Uranium silicide pellet fabrication by powder metallurgy for accident tolerant fuel evaluation and irradiation JM Harp, PA Lessing, RE Hoggan Journal of Nuclear Materials 466, 728-738, 2015 | 156 | 2015 |
| Detection and analysis of particles with failed SiC in AGR-1 fuel compacts JD Hunn, CA Baldwin, TJ Gerczak, FC Montgomery, RN Morris, CM Silva, ... Nuclear Engineering and Design 306, 36-46, 2016 | 99 | 2016 |
| Scanning electron microscopy examination of a Fast Flux Test Facility irradiated U-10Zr fuel cross section clad with HT-9 JM Harp, DL Porter, BD Miller, TL Trowbridge, WJ Carmack Journal of Nuclear Materials 494, 227-239, 2017 | 75 | 2017 |
| Irradiation performance of AGR-1 high temperature reactor fuel PA Demkowicz, JD Hunn, SA Ploger, RN Morris, CA Baldwin, JM Harp, ... Nuclear Engineering and Design 306, 2-13, 2016 | 75 | 2016 |
| Uranium nitride tristructural-isotropic fuel particle KA Terrani, BC Jolly, JM Harp Journal of Nuclear Materials 531, 152034, 2020 | 71 | 2020 |
| Initial examination of fuel compacts and TRISO particles from the US AGR-2 irradiation test JD Hunn, CA Baldwin, FC Montgomery, TJ Gerczak, RN Morris, ... Nuclear Engineering and Design 329, 89-101, 2018 | 58 | 2018 |
| An analysis of nuclear fuel burnup in the AGR-1 TRISO fuel experiment using gamma spectrometry, mass spectrometry, and computational simulation techniques JM Harp, PA Demkowicz, PL Winston, JW Sterbentz Nuclear Engineering and Design 278, 395-405, 2014 | 51 | 2014 |
| Thermal and transport properties of U3Si2 DJ Antonio, K Shrestha, JM Harp, CA Adkins, Y Zhang, J Carmack, ... Journal of Nuclear Materials 508, 154-158, 2018 | 50 | 2018 |
| Postirradiation examinations of low burnup U3Si2 fuel for light water reactor applications F Cappia, JM Harp Journal of Nuclear Materials 518, 62-79, 2019 | 49 | 2019 |
| A critical review of high burnup fuel fragmentation, relocation, and dispersal under loss-of-coolant accident conditions N Capps, C Jensen, F Cappia, J Harp, K Terrani, N Woolstenhulme, ... Journal of Nuclear Materials 546, 152750, 2021 | 46 | 2021 |
| Postirradiation examination results of several metallic fuel alloys and forms from low burnup AFC irradiations JM Harp, HJM Chichester, L Capriotti Journal of Nuclear Materials 509, 377-391, 2018 | 46 | 2018 |
| Bubble morphology in U3Si2 implanted by high-energy Xe ions at 300 C Y Miao, J Harp, K Mo, S Zhu, T Yao, J Lian, AM Yacout Journal of Nuclear Materials 495, 146-153, 2017 | 42 | 2017 |
| Preliminary results of post-irradiation examination of the AGR-1 TRISO fuel compacts P Demkowicz, J Hunn, R Morris, J Harp, P Winston, C Baldwin, ... Idaho National Lab.(INL), Idaho Falls, ID (United States), 2012 | 41 | 2012 |
| Spark plasma sintering (SPS) densified U3Si2 pellets: Microstructure control and enhanced mechanical and oxidation properties B Gong, T Yao, P Lei, J Harp, AT Nelson, J Lian Journal of Alloys and Compounds 825, 154022, 2020 | 40 | 2020 |
| Short Communication on “In-situ TEM ion irradiation investigations on U3Si2 at LWR temperatures” Y Miao, J Harp, K Mo, S Bhattacharya, P Baldo, AM Yacout Journal of Nuclear Materials 484, 168-173, 2017 | 39 | 2017 |
| 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 |
| Radiation-induced grain subdivision and bubble formation in U3Si2 at LWR temperature T Yao, B Gong, L He, J Harp, M Tonks, J Lian Journal of Nuclear Materials 498, 169-175, 2018 | 32 | 2018 |
| U3Si2 and UO2 composites densified by spark plasma sintering for accident-tolerant fuels B Gong, T Yao, P Lei, L Cai, KE Metzger, EJ Lahoda, FA Boylan, ... Journal of Nuclear Materials 534, 152147, 2020 | 29 | 2020 |
| Microstructure investigations of U3Si2 implanted by high-energy Xe ions at 600° C Y Miao, J Harp, K Mo, YS Kim, S Zhu, AM Yacout Journal of Nuclear Materials 503, 314-322, 2018 | 29 | 2018 |
| On spinodal-like phase decomposition in U–50Zr alloy T Yao, AR Wagner, X Liu, EIA Anter, JM Harp, J Gan, DH Hurley, ... Materialia 9, 100592, 2020 | 27 | 2020 |
Luca CapriottiIdaho National laboratoryVerified email at inl.gov
