| Assessment of radiation-induced segregation mechanisms in austenitic and ferritic–martensitic alloys GS Was, JP Wharry, B Frisbie, BD Wirth, D Morgan, JD Tucker, TR Allen Journal of Nuclear Materials 411 (1-3), 41-50, 2011 | 170 | 2011 |
| Application of STEM characterization for investigating radiation effects in BCC Fe-based alloys CM Parish, KG Field, AG Certain, JP Wharry Journal of Materials Research 30 (9), 1275-1289, 2015 | 123 | 2015 |
| A review of the irradiation evolution of dispersed oxide nanoparticles in the bcc Fe-Cr system: Current understanding and future directions JP Wharry, MJ Swenson, KH Yano Journal of Nuclear Materials 486, 11-20, 2017 | 115 | 2017 |
| A systematic study of radiation-induced segregation in ferritic–martensitic alloys JP Wharry, GS Was Journal of Nuclear Materials 442 (1-3), 7-16, 2013 | 96 | 2013 |
| The mechanism of radiation-induced segregation in ferritic–martensitic alloys JP Wharry, GS Was Acta Materialia 65, 42-55, 2014 | 93 | 2014 |
| Plastic zone size for nanoindentation of irradiated Fe–9% Cr ODS CK Dolph, DJ da Silva, MJ Swenson, JP Wharry Journal of Nuclear Materials 481, 33-45, 2016 | 89 | 2016 |
| The comparison of microstructure and nanocluster evolution in proton and neutron irradiated Fe–9% Cr ODS steel to 3 dpa at 500 C MJ Swenson, JP Wharry Journal of nuclear materials 467, 97-112, 2015 | 73 | 2015 |
| Radiation-induced segregation and phase stability in ferritic–martensitic alloy T 91 JP Wharry, Z Jiao, V Shankar, JT Busby, GS Was Journal of nuclear materials 417 (1-3), 140-144, 2011 | 70 | 2011 |
| Nanocluster irradiation evolution in Fe-9% Cr ODS and ferritic-martensitic alloys MJ Swenson, JP Wharry Journal of Nuclear Materials 496, 24-40, 2017 | 62 | 2017 |
| Application of the inverse Kirkendall model of radiation-induced segregation to ferritic–martensitic alloys JP Wharry, Z Jiao, GS Was Journal of nuclear materials 425 (1-3), 117-124, 2012 | 56 | 2012 |
| Thermal energy transport in oxide nuclear fuel DH Hurley, A El-Azab, MS Bryan, MWD Cooper, CA Dennett, K Gofryk, ... Chemical Reviews 122 (3), 3711-3762, 2021 | 51 | 2021 |
| The effects of oxide evolution on mechanical properties in proton-and neutron-irradiated Fe-9% Cr ODS steel MJ Swenson, CK Dolph, JP Wharry Journal of Nuclear Materials 479, 426-435, 2016 | 50 | 2016 |
| Intrinsic-extrinsic size effect relationship for micromechanical tests JP Wharry, KH Yano, PV Patki Scripta Materialia 162, 63-67, 2019 | 49 | 2019 |
| Grain orientation dependence of nanoindentation and deformation-induced martensitic phase transformation in neutron irradiated AISI 304L stainless steel KS Mao, C Sun, Y Huang, CH Shiau, FA Garner, PD Freyer, JP Wharry Materialia 5, 100208, 2019 | 49 | 2019 |
| Effects of proton irradiation on structural and electrochemical charge storage properties of TiO 2 nanotube electrodes for lithium-ion batteries KA Smith, AI Savva, C Deng, JP Wharry, S Hwang, D Su, Y Wang, J Gong, ... Journal of materials chemistry A 5 (23), 11815-11824, 2017 | 47 | 2017 |
| Microstructure-property relationship for AISI 304/308L stainless steel laser weldment K Mao, H Wang, Y Wu, V Tomar, JP Wharry Materials Science and Engineering: A 721, 234-243, 2018 | 46 | 2018 |
| TEM in situ micropillar compression tests of ion irradiated oxide dispersion strengthened alloy KH Yano, MJ Swenson, Y Wu, JP Wharry Journal of Nuclear Materials 483, 107-120, 2017 | 43 | 2017 |
| Characterization of microstructure and property evolution in advanced cladding and duct: Materials exposed to high dose and elevated temperature TR Allen, D Kaoumi, JP Wharry, Z Jiao, C Topbasi, A Kohnert, L Barnard, ... Journal of Materials Research 30 (9), 1246-1274, 2015 | 40 | 2015 |
| TEM characterization of irradiated microstructure of Fe-9% Cr ODS and ferritic-martensitic alloys MJ Swenson, JP Wharry Journal of Nuclear Materials 502, 30-41, 2018 | 32 | 2018 |
| Investing in a permanent and sustainable nuclear waste disposal solution KH Yano, KS Mao, JP Wharry, DM Porterfield Progress in Nuclear Energy 108, 474-479, 2018 | 28 | 2018 |
