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 | 54 | 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 Lab.(ORNL), Oak Ridge, TN (United States), 2018 | 20 | 2018 |
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 | 14 | 2021 |
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 | 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 | 7 | 2022 |
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 | 6 | 2023 |
Transportation Planning for Irradiated Fuel-Cladding and Integral FeCrAl Experiments AG Le Coq, RC Martin, KD Linton Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2019 | 6 | 2019 |
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 Lab.(ORNL), Oak Ridge, TN (United States), 2018 | 6 | 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 Lab.(ORNL), Oak Ridge, TN (United States), 2021 | 5 | 2021 |
Wireless Instrumented RB Experiment Preliminary Design and Analysis PL Mulligan, KR Smith, ND Bull-Ezell, DC Sweeney, KM Godsey, ... Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States); Westinghouse …, 2020 | 5 | 2020 |
Assembly of MiniFuel Targets for Irradiation of U-Mo Fuel Specimens in the High Flux Isotope Reactor A Le Coq, RC Gallagher, K Godsey, C Massey, J Harp, A Nelson Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2021 | 4 | 2021 |
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 Lab.(ORNL), Oak Ridge, TN (United States), 2018 | 4 | 2018 |
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 Lab.(ORNL), Oak Ridge, TN (United States), 2021 | 3 | 2021 |
Design of a safeguards instrument for plutonium quantification in an electrochemical refining system AG Le Coq | 3 | 2013 |
Status Report on Irradiation of MiniFuel Targets Bearing TRISO Fuel Compacts AG Le Coq, JP Gorton, ZG Wallen, TJ Gerczak, KD Linton Oak Ridge National Laboratory, ORNL/TM-2022/2456, 2022 | 2 | 2022 |
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 Lab.(ORNL), Oak Ridge, TN (United States), 2021 | 2 | 2021 |
Thermal Analysis and Irradiation Growth of Coated Zirconium Alloy Cladding Specimens in HFIR PA Champlin, CM Petrie, AG Le Coq, KR Smith, KD Linton Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States). High Flux …, 2020 | 2 | 2020 |
HFIR Irradiation Testing Supporting the Transformational Challenge Reactor A Le Coq, K Linton, P Champlin, RH Howard, X Hu, TS Byun, K Terrani Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2020 | 2 | 2020 |
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 Lab.(ORNL), Oak Ridge, TN (United States), 2020 | 2 | 2020 |
Design and Thermal Analysis for Irradiation of Absorber Material Specimens in the High Flux Isotope Reactor NO Cetiner, CM Petrie, JR Burns, AG Le Coq, KD Linton, J Stevens Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2018 | 2 | 2018 |