| Evaluation of the continuous dilatometer method of silicon carbide thermometry for passive irradiation temperature determination KG Field, JL McDuffee, JW Geringer, CM Petrie, Y Katoh Nuclear Instruments and Methods in Physics Research Section B: Beam …, 2019 | 58 | 2019 |
| Neutron irradiation effects on the mechanical properties of powder metallurgical processed tungsten alloys T Miyazawa, LM Garrison, JW Geringer, M Fukuda, Y Katoh, T Hinoki, ... Journal of Nuclear Materials 529, 151910, 2020 | 36 | 2020 |
| Phenix US-Japan collaboration investigation of thermal and mechanical properties of thermal neutron–shielded irradiated tungsten LM Garrison, Y Katoh, JW Geringer, M Akiyoshi, X Chen, M Fukuda, ... Fusion Science and Technology 75 (6), 499-509, 2019 | 35 | 2019 |
| Investigation of mechanical and microstructural properties of Zircaloy-4 under different experimental conditions CM Silva, KJ Leonard, E Van Abel, JW Geringer, CD Bryan Journal of Nuclear Materials 499, 546-557, 2018 | 26 | 2018 |
| The status of the Japanese material properties handbook and the challenge to facilitate structural design criteria for DEMO in-vessel components T Nozawa, H Tanigawa, T Kojima, T Itoh, N Hiyoshi, M Ohata, T Kato, ... Nuclear Fusion 61 (11), 116054, 2021 | 24 | 2021 |
| Tensile properties of powder-metallurgical-processed tungsten alloys after neutron irradiation near recrystallization temperatures T Miyazawa, LM Garrison, JW Geringer, JR Echols, M Fukuda, Y Katoh, ... Journal of Nuclear Materials 542, 152505, 2020 | 22 | 2020 |
| Non-contact strain evaluation for miniature tensile specimens of neutron-irradiated F82H by digital image correlation T Nozawa, H Sakasegawa, X Chen, T Kato, JW Geringer, Y Katoh, ... Fusion Engineering and Design 157, 111663, 2020 | 22 | 2020 |
| Progress in the US/Japan PHENIX project for the technological assessment of plasma facing components for DEMO reactors Y Katoh, D Clark, Y Ueda, Y Hatano, M Yoda, AS Sabau, T Yokomine, ... Fusion Science and Technology 72 (3), 222-232, 2017 | 21 | 2017 |
| Technological aspects in blanket design: Effects of micro-alloying and thermo-mechanical treatments of EUROFER97 type steels after neutron irradiation M Rieth, E Simondon, G Pintsuk, G Aiello, J Henry, D Terentyev, A Puype, ... Fusion Engineering and Design 168, 112645, 2021 | 19 | 2021 |
| Thermal diffusivity of irradiated tungsten and tungsten-rhenium alloys M Akiyoshi, LM Garrison, JW Geringer, H Wang, A Hasegawa, S Nogami, ... Journal of Nuclear Materials 543, 152594, 2021 | 19 | 2021 |
| Determination of neutron irradiation temperatures of SiC using electrical resistivity method H Wang, T Koyanagi, JW Geringer, AA Campbell, Y Katoh Journal of Nuclear Materials 540, 152370, 2020 | 16 | 2020 |
| Irradiation performance of rare earth and nanoparticle enhanced high temperature superconducting films based on YBCO KJ Leonard, FA List III, T Aytug, AA Gapud, JW Geringer Nuclear Materials and Energy 9, 251-255, 2016 | 16 | 2016 |
| Irradiation hardening and ductility loss of Eurofer97 steel variants after neutron irradiation to ITER-TBM relevant conditions A Bhattacharya, X Chen, T Graening, JW Geringer, J Reed, J Henry, ... Fusion Engineering and Design 173, 112935, 2021 | 13 | 2021 |
| Effects of HFIR neutron irradiation on fracture toughness properties of standard and Ni-doped F82H XC Frank, MA Sokolov, J Robertson, M Ando, JW Geringer, H Tanigawa, ... Journal of Nuclear Materials 542, 152501, 2020 | 13 | 2020 |
| Validation of miniature test specimens for post-irradiation thermal diffusivity measurement M Akiyoshi, R Kasada, Y Ishibashi, LM Garrison, JW Geringer, WD Porter, ... Fusion Engineering and Design 136, 513-517, 2018 | 9 | 2018 |
| Conceptual design of HFIR irradiation experiment for material compatibility study on liquid Sn divertor M Kondo, BA Pint, J Jun, N Russell, J McDUFFEE, M Akiyoshi, T Tanaka, ... Plasma and Fusion Research 16, 2405040-2405040, 2021 | 7 | 2021 |
| Strain evaluation using a non-contact deformation measurement system in tensile tests of irradiated F82H and 9cr ODS steels H Sakasegawa, X Chen, T Kato, H Tanigawa, M Ando, JW Geringer, ... Nuclear Materials and Energy 16, 108-113, 2018 | 6 | 2018 |
| SiC/SiC Composites Technology Gap Analysis for Molten Salt Reactors JW Geringer, Y Katoh, T Koyanagi, Y Lee Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2018 | 6 | 2018 |
| Equibiaxial Flexure Strength of a Superfine-Grained Nuclear Graphite AA Campbell, AA Wereszczak, JW Geringer, Y Katoh Graphite Testing for Nuclear Applications: The Validity and Extension of …, 2022 | 4 | 2022 |
| Codes and standards for ceramic composite core materials for High Temperature Reactor applications JW Geringer, Y Katoh, S Gonczy, T Burchell, M Mitchell, M Jenkins, ... Nuclear Engineering and Design 405, 112158, 2023 | 3 | 2023 |
