| Development of low-Cr ODS FeCrAl alloys for accident-tolerant fuel cladding S Dryepondt, KA Unocic, DT Hoelzer, CP Massey, BA Pint Journal of Nuclear Materials 501, 59-71, 2018 | 139 | 2018 |
| Cladding burst behavior of Fe-based alloys under LOCA CP Massey, KA Terrani, SN Dryepondt, BA Pint Journal of Nuclear Materials 470, 128-138, 2016 | 128 | 2016 |
| Multiscale investigations of nanoprecipitate nucleation, growth, and coarsening in annealed low-Cr oxide dispersion strengthened FeCrAl powder CP Massey, SN Dryepondt, PD Edmondson, MG Frith, KC Littrell, A Kini, ... Acta Materialia 166, 1-17, 2019 | 57 | 2019 |
| Influence of mechanical alloying and extrusion conditions on the microstructure and tensile properties of Low-Cr ODS FeCrAl alloys CP Massey, SN Dryepondt, PD Edmondson, KA Terrani, SJ Zinkle Journal of Nuclear Materials 512, 227-238, 2018 | 50 | 2018 |
| Strength and rupture geometry of un-irradiated C26M FeCrAl under LOCA burst testing conditions SB Bell, KA Kane, CP Massey, LA Baldesberger, D Lutz, BA Pint Journal of Nuclear Materials 557, 153242, 2021 | 48 | 2021 |
| Improved irradiation resistance of accident-tolerant high-strength FeCrAl alloys with heterogeneous structures KS Mao, CP Massey, Y Yamamoto, KA Unocic, MN Gussev, D Zhang, ... Acta Materialia 231, 117843, 2022 | 29 | 2022 |
| Modern nanostructured ferritic alloys: A compelling and viable choice for sodium fast reactor fuel cladding applications DT Hoelzer, CP Massey, SJ Zinkle, DC Crawford, KA Terrani Journal of Nuclear Materials 529, 151928, 2020 | 29 | 2020 |
| The effect of Zr on precipitation in oxide dispersion strengthened FeCrAl alloys CP Massey, PD Edmondson, KA Unocic, Y Yang, SN Dryepondt, A Kini, ... Journal of Nuclear Materials 533, 152105, 2020 | 28 | 2020 |
| Post irradiation examination of nanoprecipitate stability and α′ precipitation in an oxide dispersion strengthened Fe-12Cr-5Al alloy CP Massey, PD Edmondson, KG Field, DT Hoelzer, SN Dryepondt, ... Scripta Materialia 162, 94-98, 2019 | 28 | 2019 |
| Ultrasonic additive manufacturing of zirconium: Pilot results CP Massey, CJ Havrilak, MN Gussev, KA Terrani, AT Nelson Materials Letters 302, 130330, 2021 | 27 | 2021 |
| Effect of heavy ion irradiation dose rate and temperature on α′ precipitation in high purity Fe-18% Cr alloy Y Zhao, A Bhattacharya, C Pareige, C Massey, P Zhu, JD Poplawsky, ... Acta Materialia 231, 117888, 2022 | 25 | 2022 |
| Deconvoluting the effect of chromium and aluminum on the radiation response of wrought FeCrAl alloys after low-dose neutron irradiation CP Massey, D Zhang, SA Briggs, PD Edmondson, Y Yamamoto, ... Journal of Nuclear Materials 549, 152804, 2021 | 24 | 2021 |
| Investigation of deformation mechanisms in an advanced FeCrAl alloy using in-situ SEM-EBSD testing N Bibhanshu, MN Gussev, CP Massey, KG Field Materials Science and Engineering: A 832, 142373, 2022 | 20 | 2022 |
| Investigations of aluminum-doped self-healing Zircaloy surfaces in context of accident-tolerant fuel cladding research J Carr, G Vasudevamurthy, L Snead, B Hinderliter, C Massey Journal of Materials Engineering and Performance 25, 2347-2355, 2016 | 19 | 2016 |
| The response of accident tolerant fuel cladding to LOCA burst testing: A comparative study of leading concepts K Kane, S Bell, N Capps, B Garrison, K Shapovalov, G Jacobsen, C Deck, ... Journal of Nuclear Materials 574, 154152, 2023 | 18 | 2023 |
| Stability of a model Fe-14Cr nanostructured ferritic alloy after long-term thermal creep CP Massey, DT Hoelzer, PD Edmondson, A Kini, B Gault, KA Terrani, ... Scripta Materialia 170, 134-139, 2019 | 18 | 2019 |
| Microstructural evaluation of a Fe-12Cr nanostructured ferritic alloy designed for impurity sequestration CP Massey, DT Hoelzer, RL Seibert, PD Edmondson, A Kini, B Gault, ... Journal of Nuclear Materials 522, 111-122, 2019 | 15 | 2019 |
| FeCrAl fuel/clad chemical interaction in light water reactor environments HJ Qu, M Higgins, H Abouelella, F Cappia, J Burns, L He, C Massey, ... Journal of Nuclear Materials 587, 154717, 2023 | 14 | 2023 |
| Deuterium retention in advanced steels for fusion reactor structural application X Hu, L Tan, K Wang, CP Massey, DT Hoelzer, Y Katoh Journal of Nuclear Materials 516, 144-151, 2019 | 14 | 2019 |
| Insights from microstructure and mechanical property comparisons of three pilgered ferritic ODS tubes CP Massey, PD Edmondson, MN Gussev, K Mao, T Gräning, TJ Nizolek, ... Materials & Design 213, 110333, 2022 | 13 | 2022 |
Sebastien DryepondtORNLПодтвержден адрес электронной почты в домене ornl.gov