| Thermo-mechanical assessment of full SiC/SiC composite cladding for LWR applications with sensitivity analysis G Singh, K Terrani, Y Katoh Journal of Nuclear Materials 499, 126-143, 2018 | 69 | 2018 |
| SiC/SiC Cladding Materials Properties Handbook T Koyanagi, Y Katoh, GP Singh, MA Snead Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2017 | 62* | 2017 |
| Parametric evaluation of SiC/SiC composite cladding with UO2 fuel for LWR applications: Fuel rod interactions and impact of nonuniform power profile in fuel rod G Singh, R. Sweet, N. Brown, B. Wirth, Y. Katoh, K. Terrani Journal of Nuclear Materials, 2017 | 50* | 2017 |
| Interlaboratory round robin study on axial tensile properties of SiC‐SiC CMC tubular test specimens G Singh, S Gonczy, C Deck, E Lara‐Curzio, Y Katoh International Journal of Applied Ceramic Technology 15 (6), 1334-1349, 2018 | 35 | 2018 |
| Fracture behavior of nuclear graphite NBG-18 H Li, J Li, G Singh, A Fok Carbon 60, 46-56, 2013 | 35 | 2013 |
| Determination of the tension softening curve of nuclear graphites using the incremental displacement collocation method RKL Su, HH Chen, SL Fok, H Li, G Singh, L Sun, L Shi Carbon 57, 65-78, 2013 | 34 | 2013 |
| Failure behavior of SiC/SiC composite tubes under strain rates similar to the pellet-cladding mechanical interaction phase of reactivity-initiated accidents MN Cinbiz, T Koyanagi, G Singh, Y Katoh, KA Terrani, NR Brown Journal of Nuclear Materials 514, 66-73, 2019 | 30 | 2019 |
| Deformation analysis of SiC-SiC channel box for BWR applications G Singh, J Gorton, D Schappel, NR Brown, Y Katoh, BD Wirth, KA Terrani Journal of Nuclear Materials 513, 71-85, 2019 | 25 | 2019 |
| Elastic moduli reduction in SiC-SiC tubular specimen after high heat flux neutron irradiation measured by resonant ultrasound spectroscopy G Singh, T Koyanagi, C Petrie, C Deck, K Terrani, JD Arregui-Mena, ... Journal of Nuclear Materials 523, 391-401, 2019 | 20 | 2019 |
| Evaluating the irradiation effects on the elastic properties of miniature monolithic SiC tubular specimens G Singh, T. Koyanagi, C. Petrie, K. Terrani, Y. Katoh Journal of Nuclear Materials, 2017 | 18* | 2017 |
| Efficient high-fidelity TRISO statistical failure analysis using Bison: Applications to AGR-2 irradiation testing W Jiang, G Singh, JD Hales, A Toptan, BW Spencer, SR Novascone, ... Journal of Nuclear Materials 562, 153585, 2022 | 15 | 2022 |
| Failure predictions for graphite reflector bricks in the very high temperature reactor with the prismatic core design G Singh, A Fok, S Mantell Nuclear Engineering and Design 317, 190-198, 2017 | 15 | 2017 |
| Preliminary study of sintering zero‐rupture Fully Ceramic Microencapsulated (FCM) fuel C Ang, G Singh, L Snead, Y Katoh International Journal of Applied Ceramic Technology 16 (5), 1699-1707, 2019 | 13 | 2019 |
| Measuring the elastic tensor of a monolithic SiC hollow cylinder with resonant ultrasound spectroscopy CM Donahue, MC Remillieux, G Singh, TJ Ulrich, RJ Migliori, TA Saleh NDT & E International 101, 29-33, 2019 | 11 | 2019 |
| Impact of control blade insertion on the deformation behavior of SiC-SiC channel boxes in BWRs G Singh, JP Gorton, D Schappel, BS Collins, Y Katoh, NR Brown, ... Nuclear Engineering and Design 363, 110621, 2020 | 8 | 2020 |
| Fracture behavior of degraded polyethylene thin films for solar thermal applications H Ge, G Singh, SC Mantell Energy Procedia 30, 783-792, 2012 | 8 | 2012 |
| Efficient failure probability calculations and modeling interface debonding in TRISO particles with BISON W Jiang, G Singh, JD Hales, A Toptan, BW Spencer, SR Novascone Idaho National Lab.(INL), Idaho Falls, ID (United States), 2021 | 7 | 2021 |
| Determination of He and D permeability of neutron-irradiated SiC tubes to examine the potential for release due to micro-cracking X Hu, T Koyanagi, GP Singh, Y Katoh ORNL-SR-2017/362)(Oak Ridge, TN: Oak Ridge National Laboratory, 2017), 2017 | 7 | 2017 |
| Prediction of degradation of polyolefins used in solar domestic hot water components W Camisa, SC Mantell, JH Davidson, G Singh Energy Sustainability 43956, 301-308, 2010 | 5 | 2010 |
| Irradiation High Heat Flux Synergism in Silicon Carbide-Based Fuel Claddings for Light Water Reactors Y Katoh, KA Terrani, T Koyanagi, CM Petrie, GP Singh, LL Snead, ... Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States). High …, 2017 | 4 | 2017 |
Yutai KatohMaterials Science and Technology Division, Oak Ridge National Laboratory在 ornl.gov 的电子邮件经过验证
