| 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 | 56 | 2021 |
| 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 | 55 | 2015 |
| 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 | 35 | 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 | 25 | 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 | 16 | 2019 |
| 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 | 15 | 2021 |
| 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 | 15 | 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 | 14 | 2020 |
| 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 | 12 | 2019 |
| 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 | 11 | 2022 |
| 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 |
| (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 | 9 | 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 | 9 | 2019 |
| BISON validation of FeCrAl cladding mechanical failure during simulated reactivity-initiated accident conditions SK Lee, BE Garrison, NA Capps, G Pastore, CP Massey, KD Linton, ... Journal of Nuclear Materials 564, 153676, 2022 | 8 | 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 | 7 | 2023 |
| Quantifying deformation during Zry-4 burst testing: a comparison of BISON and a combined in-situ digital image correlation and infrared thermography method K Kane, S Bell, B Garrison, M Ridley, M Gussev, K Linton, N Capps Journal of Nuclear Materials 572, 154063, 2022 | 7 | 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 | 7 | 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 | 7 | 2021 |
| 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 | 7 | 2017 |
| TREAT testing of additively manufactured SiC canisters loaded with high density TRISO fuel for the Transformational Challenge Reactor project N Woolstenhulme, D Chapman, N Cordes, A Fleming, C Hill, C Jensen, ... Journal of Nuclear Materials 575, 154204, 2023 | 6 | 2023 |
