| LAMDA: irradiated-materials microscopy at Oak Ridge National Laboratory CM Parish, NAPK Kumar, LL Snead, PD Edmondson, KG Field, C Silva, ... Microscopy and Microanalysis 21 (S3), 1003-1004, 2015 | 52 | 2015 |
| 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 | 26 | 2021 |
| Integral LOCA fragmentation test on high-burnup fuel N Capps, Y Yan, A Raftery, Z Burns, T Smith, K Terrani, K Yueh, M Bales, ... Nuclear Engineering and Design 367, 110811, 2020 | 22 | 2020 |
| Mechanical properties and microstructure characterization of Eurofer97 steel variants in EUROfusion program X Chen, A Bhattacharya, MA Sokolov, LN Clowers, Y Yamamoto, ... Fusion Engineering and Design 146, 2227-2232, 2019 | 21 | 2019 |
| An advanced experimental design for modified burst testing of nuclear fuel cladding materials during transient loading MN Cinbiz, M Gussev, K Linton, KA Terrani Annals of Nuclear Energy 127, 30-38, 2019 | 13 | 2019 |
| Report on Design and Failure Limits of SiC/SiC and FeCrAl ATF Cladding Concepts under RIA MN Cinbiz, N Brown, RR Lowden, MN Gussev, KD Linton, KA Terrani Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2018 | 13 | 2018 |
| Mechanical failure of fresh nuclear grade iron–chromium–aluminum (FeCrAl) cladding under simulated hot zero power reactivity initiated accident conditions NR Brown, BE Garrison, RR Lowden, MN Cinbiz, KD Linton Journal of Nuclear Materials 539, 152352, 2020 | 11 | 2020 |
| 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 | 9 | 2021 |
| Capsule and Specimen Geometries for HFIR Irradiation Testing Supporting the Transformational Challenge Reactor P Champlin, J Burns, CM Petrie, X Hu, K Linton, RH Howard, K Terrani Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2021 | 9 | 2021 |
| (S) TEM/EDS study of native precipitates and irradiation induced Nb-rich platelets in high-burnup M5® Z Yu, JW Werden, NA Capps, KD Linton, A Couet Journal of Nuclear Materials 544, 152667, 2021 | 8 | 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 | 7 | 2021 |
| LOCA Fragmentation Test with High Burnup HBR Fuel Rod Y Yan, ZM Burns, TS Smith, KD Linton, K Yueh, KA Terrani Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2019 | 6 | 2019 |
| Transition fracture toughness characterization of Eurofer97 steel using pre-cracked miniature multi-notch bend bar specimens X Chen, MA Sokolov, KD Linton, LN Clowers, Y Katoh ORNL/LTR-2017/532, November 30, 2017 | 6 | 2017 |
| Burst characteristics of advanced accident-tolerant FeCrAl cladding under temperature transient testing B Garrison, MN Cinbiz, M Gussev, K Linton Journal of Nuclear Materials 560, 153488, 2022 | 5 | 2022 |
| Report on Design and Failure Limits of SiC MN Cinbiz, N Brown, RR Lowden, MN Gussev, KD Linton, KA Terrani SiC and FeCrAl ATF Cladding Concepts under RIA, Oak Ridge, TN (United States), 2018 | 5 | 2018 |
| Hot Cell Installation and Demonstration of the Severe Accident Test Station KD Linton, ZM Burns, KA Terrani, Y Yan Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2017 | 5 | 2017 |
| Post-Irradiation Fracture Toughness Characterization of Generation II FeCrAl Alloys X Chen, KG Field, R Howard, CP Massey, AT Nelson Pressure Vessels and Piping Conference 86182, V04BT06A019, 2022 | 4 | 2022 |
| 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 | 4 | 2022 |
| Development and Implementation of Digital Image Correlation for Out-of-Cell Burst Testing K Kane, N Capps, B Garrison, B Johnston, S Bell, K Linton Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2021 | 4 | 2021 |
| Handbook on the Material Properties of Yttrium Hydride for High Temperature Moderator Applications X Hu, H Wang, K Linton, A Le Coq, K Terrani Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2021 | 4 | 2021 |
