| Enhanced thermal conductivity of uranium dioxide–silicon carbide composite fuel pellets prepared by Spark Plasma Sintering (SPS) S Yeo, E Mckenna, R Baney, G Subhash, J Tulenko Journal of Nuclear Materials 433 (1-3), 66-73, 2013 | 142 | 2013 |
| The influence of SiC particle size and volume fraction on the thermal conductivity of spark plasma sintered UO2–SiC composites S Yeo, R Baney, G Subhash, J Tulenko Journal of nuclear materials 442 (1-3), 245-252, 2013 | 58 | 2013 |
| Comparison of diffusion coefficients and activation energies for Ag diffusion in silicon carbide BG Kim, S Yeo, YW Lee, MS Cho Nuclear Engineering and Technology 47 (5), 608-616, 2015 | 25 | 2015 |
| Fabrication methods and anisotropic properties of graphite matrix compacts for use in HTGR S Yeo, J Yun, S Kim, MS Cho, YW Lee Journal of Nuclear Materials 499, 383-393, 2018 | 19 | 2018 |
| Synthesis of plasma-nitrided Cr coatings on HT9 steel for advanced chemical barrier property in a nuclear cladding application S Yeo, CM Lee, HS Yoon, JH Kim Applied Surface Science 579, 152133, 2022 | 13 | 2022 |
| The characterization of electrodeposited chromium barriers for nuclear reactor cladding application S Yeo, JH Kim, SH Eom Journal of Nuclear Materials 530, 151980, 2020 | 13 | 2020 |
| Phase evolution of (Ni, Co, Mn) O4 during heat treatment with high temperature in situ X-ray diffraction S Mhin, HS Han, D Kim, S Yeo, JI Lee, JH Ryu Ceramics International 42 (4), 5412-5417, 2016 | 12 | 2016 |
| CoFeS2@CoS2 Nanocubes Entangled with CNT for Efficient Bifunctional Performance for Oxygen Evolution and Oxygen Reduction Reactions J Jeon, KR Park, KM Kim, D Ko, HS Han, N Oh, S Yeo, C Ahn, S Mhin Nanomaterials 12 (6), 983, 2022 | 9 | 2022 |
| High density UO2 and high thermal conductivity UO2 composites by spark plasma sintering (SPS) G Subhash, RH Baney, JS Tulenko, E Mckenna III, L Ge, S Yeo US Patent 10,790,065, 2020 | 8 | 2020 |
| Synthesis of CoxMn1− xO4 (0.9≤ x≤ 2.7) nanopowders with controlled phase and composition via a gel-combustion method HS Han, JS Lee, J Lim, KR Park, KM Kim, JH Ryu, S Yeo, J Forrester, ... Ceramics International 42 (15), 17168-17173, 2016 | 7 | 2016 |
| Reduced anisotropic properties of Cold Isostatic Pressed graphite matrix compacts S Yeo, YW Lee Journal of Nuclear Materials 515, 245-256, 2019 | 6 | 2019 |
| Effect of pulse current and coating thickness on the microstructure and FCCI resistance of electroplated chromium on HT9 steel cladding S Yeo, JH Kim, HS Yun Surface and Coatings Technology 389, 125652, 2020 | 5 | 2020 |
| Irradiation Testing of TRISO-Coated Particle Fuel in Korea BG Kim, S Yeo, KC Jeong, SH Eom, YK Kim, WK Kim, YW Lee, MS Cho, ... | 5 | 2014 |
| Uranium dioxide-silicon carbide composite reactor fuels with enhanced thermal and mechanical properties prepared by spark plasma sintering S Yeo University of Florida, 2013 | 5 | 2013 |
| The first irradiation testing and PIE or TRISO-coated particle fuel in Korea BG Kim, S Yeo, KC Jeong, YK Kim, YW Lee, MS Cho Nuclear Engineering and Design 329, 34-45, 2018 | 3 | 2018 |
| Fabrication Strategies and Thermal Conductivity Assessment of High Density UO2 Pellet Incorporated with SiC S Yeo, E Mckenna, R Baney, G Subhash, J Tulenko MRS Online Proceedings Library (OPL) 1444, mrss12-1444-s07-05, 2012 | 3 | 2012 |
| A study of cesium impregnation behavior in IG-110 graphite matrix by using Laser Ablation ICP-MS (LA-ICP-MS) JK Baek, HJ Ryu, SH Yeo, YW Lee, SH Han 한국원자력학회 2016 춘계학술대회, 2016 | 2 | 2016 |
| High density UO2 and high thermal conductivity UO2 composites by spark plasma sintering (SPS) G Subhash, RH Baney, JS Tulenko, E Mckenna III, L Ge, S Yeo US Patent 11,410,782, 2022 | 1 | 2022 |
| PIE Results of Irradiated TRISO-Coated Particle Fuel at HANARO BG Kim, S Yeo, KC Jeong, YK Kim, YW Lee, MS Cho Transactions of the Korean Nuclear Society Autumn Meeting, Gyeongju, Korea, 2016 | 1 | 2016 |
| Preparation of Cesium (Cs) Release Test for Verifying Diffusion Coefficient in the IG-110 Graphite Matrix JK Baek, S Yeo, YW Lee, J Lee, HJ Ryu KNS 2016 Autumn Meeting, 2016 | 1 | 2016 |
James S. TulenkoProfessor of Nuclear Engineeringufl.edu의 이메일 확인됨
