| Irradiation-enhanced α′ precipitation in model FeCrAl alloys PD Edmondson, SA Briggs, Y Yamamoto, RH Howard, K Sridharan, ... Scripta Materialia 116, 112-116, 2016 | 168 | 2016 |
| A combined APT and SANS investigation of α′ phase precipitation in neutron-irradiated model FeCrAl alloys SA Briggs, PD Edmondson, KC Littrell, Y Yamamoto, RH Howard, ... Acta Materialia 129, 217-228, 2017 | 162 | 2017 |
| Mechanical properties of neutron-irradiated model and commercial FeCrAl alloys KG Field, SA Briggs, K Sridharan, RH Howard, Y Yamamoto Journal of Nuclear Materials 489, 118-128, 2017 | 148 | 2017 |
| The development of the material plasma exposure experiment J Rapp, TM Biewer, TS Bigelow, JBO Caughman, RC Duckworth, RJ Ellis, ... IEEE Transactions on Plasma Science 44 (12), 3456-3464, 2016 | 80 | 2016 |
| Sub-size tensile specimen design for in-reactor irradiation and post-irradiation testing MN Gussev, RH Howard, KA Terrani, KG Field Nuclear Engineering and Design 320, 298-308, 2017 | 65 | 2017 |
| Heterogeneous dislocation loop formation near grain boundaries in a neutron-irradiated commercial FeCrAl alloy KG Field, SA Briggs, X Hu, Y Yamamoto, RH Howard, K Sridharan Journal of Nuclear Materials 483, 54-61, 2017 | 65 | 2017 |
| Developing the science and technology for the material plasma exposure experiment J Rapp, TM Biewer, TS Bigelow, JF Caneses, JBO Caughman, SJ Diem, ... Nuclear Fusion 57 (11), 116001, 2017 | 62 | 2017 |
| Dislocation loop formation in model FeCrAl alloys after neutron irradiation below 1 dpa KG Field, SA Briggs, K Sridharan, Y Yamamoto, RH Howard Journal of Nuclear Materials 495, 20-26, 2017 | 59 | 2017 |
| Influence of welding and neutron irradiation on dislocation loop formation and α′ precipitation in a FeCrAl alloy D Zhang, SA Briggs, PD Edmondson, MN Gussev, RH Howard, KG Field Journal of Nuclear Materials 527, 151784, 2019 | 24 | 2019 |
| Database on Performance of Neutron Irradiated FeCrAl Alloys KG Field, SA Briggs, K Littrell, CM Parish, Y Yamamoto Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States). Center for …, 2016 | 24 | 2016 |
| Assessment of near-term fuel screening and qualification needs for nuclear thermal propulsion systems K Palomares, R Howard, T Steiner Nuclear Engineering and Design 367, 110765, 2020 | 20 | 2020 |
| Mechanical performance of neutron-irradiated dissimilar transition joints of aluminum alloy 6061-T6 and 304L stainless steel RH Howard, RC Gallagher, KG Field Journal of Nuclear Materials 508, 348-353, 2018 | 18 | 2018 |
| Evaluation of the Effect of Composition on Radiation Hardening and Embrittlement in Model FeCrAl Alloys KG Field, SA Briggs, P Edmondson, X Hu, KC Littrell, R Howard, ... Oak Ridge, 2015 | 18 | 2015 |
| First annual progress report on radiation tolerance of controlled fusion welds in high temperature oxidation resistant FeCrAl alloys KG Field, MN Gussev, X Hu, Y Yamamoto, RH Howard ORNL/TM-2015/770, 2015 | 17 | 2015 |
| The Material Plasma Exposure eXperiment MPEX: Pre-design, development and testing of source concept J Rapp, TM Biewer, T Bigelow, JBO Caughman, R Duckworth, D Giuliano, ... 2015 IEEE 26th Symposium on Fusion Engineering (SOFE), 1-8, 2015 | 14 | 2015 |
| Capsule and Specimen Geometries for HFIR Irradiation Testing Supporting the Transformational Challenge Reactor P Champlin, J Burns, CM Petrie, X Hu, KD Linton, RH Howard, KA Terrani Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2019 | 13 | 2019 |
| Stability of model Fe-Cr-Al alloys under the presence of neutron radiation KG Field, X Hu, K Littrell, Y Yamamoto, RH Howard, LL Snead Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States). High Flux …, 2014 | 12 | 2014 |
| Steady-State In-Pile Nuclear Thermal Propulsion Experimental Testbed Initial Demonstration at The Ohio State University Research Reactor TR Steiner, EN Hutchins, RH Howard Nuclear Technology 208 (1), 100-114, 2022 | 10 | 2022 |
| Experimental plan and irradiation target design for FeCrAl embrittlement screening tests conducted using the high flux isotope reactor KG Field, RH Howard, Y Yamamoto Oak Ridge National Laboratory, nd, 2015 | 10 | 2015 |
| 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 | 9 | 2023 |
Kevin FieldUniversity of MichiganVerified email at umich.edu
