| Mechanical behavior of additively manufactured and wrought 316L stainless steels before and after neutron irradiation TS Byun, BE Garrison, MR McAlister, X Chen, MN Gussev, TG Lach, ... Journal of Nuclear Materials 548, 152849, 2021 | 81 | 2021 |
| Irradiation of miniature fuel specimens in the high flux isotope reactor CM Petrie, JR Burns, RN Morris, KR Smith, AG Le Coq, KA Terrani Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States), 2018 | 21 | 2018 |
| Handbook on the Material Properties of Yttrium Hydride for High Temperature Moderator Applications X Hu, H Wang, K Linton, A Le Coq, KA Terrani Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States), 2021 | 18 | 2021 |
| Irradiation stability and thermomechanical properties of 3D-printed SiC KA Terrani, T Lach, H Wang, A Le Coq, K Linton, C Petrie, T Koyanagi, ... Journal of Nuclear Materials 551, 152980, 2021 | 16 | 2021 |
| A correlation-based approach for evaluating mechanical properties of nuclear fuel cladding tubes MN Gussev, B Garrison, C Massey, A Le Coq, K Linton, KA Terrani Journal of Nuclear Materials 574, 154192, 2023 | 12 | 2023 |
| Analysis and Design of High-Power TRISO Fuel Compact Irradiation in HFIR RC Gallagher, Z Wallen, CM Petrie, T Gerczak, AG Le Coq, K Smith, ... ORNL/TM-2020/1658, Oak Ridge National Laboratory, Oak Ridge, TN, 2021 | 11 | 2021 |
| Mechanical properties of additively manufactured 316L stainless steel before and after neutron irradiation (FY21) TS Byun, DA Collins, AG Le Coq, TG Lach, KD Linton, MN Gussev, ... Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States), 2021 | 9 | 2021 |
| Characterization of radiation damage in 3D printed SiC TG Lach, AG Le Coq, KD Linton, KA Terrani, TS Byun Journal of Nuclear Materials 559, 153459, 2022 | 8 | 2022 |
| Design and Thermal Analysis for Irradiation of Tensile Specimens from Wrought, Powder Metallurgy, and Additive Processed Alloys in the HFIR AG Le Coq, RH Howard, KD Linton, KG Field Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States), 2018 | 7 | 2018 |
| Wireless Instrumented RB Experiment Preliminary Design and Analysis PL Mulligan, KR Smith, ND Bull-Ezell, DC Sweeney, KM Godsey, ... Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States), 2020 | 6 | 2020 |
| Design and thermal analysis for irradiation of silicon carbide joint specimens in the High Flux Isotope Reactor CM Petrie, AG LeCoq, RC Gallagher, KD Linton, CP Deck Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States), 2018 | 6 | 2018 |
| Impact of nano-scale cavities on hydrogen storage and retention in yttrium hydride MN Cinbiz, T Lach, M Topsakal, A Le Coq, K Linton Materialia 32, 101933, 2023 | 5 | 2023 |
| Transportation Planning for Irradiated Fuel-Cladding and Integral FeCrAl Experiments AG Le Coq, RC Martin, KD Linton Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States), 2019 | 5 | 2019 |
| High-temperature steam oxidation study of irradiated FeCrAl defueled specimens Y Yan, J Harp, A Le Coq, C Massey, K Linton Journal of Nuclear Materials 590, 154868, 2024 | 4 | 2024 |
| Report on Evolution of Inconel 718 Following HFIR Irradiation S Taller, A Le Coq, C Massey, J Werden, M Lynch, K Linton Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States), 2022 | 4 | 2022 |
| Assembly of MiniFuel Targets for Irradiation of U-Mo Fuel Specimens in the High Flux Isotope Reactor AG Le Coq, RC Gallagher, KM Godsey, CP Massey, JM Harp, AT Nelson Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States), 2021 | 4 | 2021 |
| Mechanical and Thermophysical Properties of 3D-Printed SiC Before and After Neutron Irradiation–FY21 TS Byun, TG Lach, CM Parish, H Wang, AA Trofimov, DA Collins, ... Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States), 2021 | 4 | 2021 |
| Monolithic ATF MiniFuel Sample Capsules Ready for HFIR Insertion CM Petrie, A Le Coq, D Richardson, C Hobbs, G Helmreich, J Burns, ... Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States), 2020 | 4 | 2020 |
| Simulation of a TRISO MiniFuel irradiation experiment with data-informed uncertainty quantification JP Gorton, RC Gallagher, ZG Wallen, AG Le Coq, GW Helmreich, ... Nuclear Engineering and Design 404, 112177, 2023 | 3 | 2023 |
| Mechanical Properties of Additive Manufacturing 316L Stainless Steel Before and After Neutron Irradiation-FY 2021 TS Byun, D Collins, A Le Coq, T Lach, K Linton, M Gussev, J Werden, ... | 3 | 2021 |
Kory D. LintonOak Ridge National LaboratoryVerified email at ornl.gov