| 학술지명* | 논문명* | 주저자명* | SCI(E)구분* |
| Applied Thermal Engineering | Heat Transfer Characteristics and Operation Limit of Pressurized Hybrid Heat Pipe for Small Modular Reactors | Kyung Mo Kim, In Cheol Bang | SCI |
| International Journal of Energy Research | Risk-reduction of passive decay heat removal system by using gallium-water for UCFR and SMR | Seok Bin Seo, In Cheol Bang | SCI |
| Experimental thermal and fluid science | Hydraulic control rod drive mechanism concept for passive in-core cooling system (PINCs) in fully passive advanced nuclear power plant | In Guk Kim, In Cheol Bang | SCI |
| International Journal of Energy Research | Analysis of hydrogen and dust explosion after vacuum vessel rupture: Preliminary safety analysis of Korean fusion demonstration reactor using MELCOR | Sung Bo Moon, In Cheol Bang | SCI |
| Applied Thermal Engineering | Flow Visualization and Heat Transfer Performance of Annular Thermosyphon Heat Pipe | In Guk Kim, In Cheol Bang | SCI |
| Journal of Alloys and Compounds | Enhancement of corrosion resistance in carbon steels using nickel-phosphorous/titanium dioxide nanocomposite coatings under high-temperature flowing water | Seunghyun Kim | SCI |
| Scientific Reports | Effect of defects on reaction of NiO surface with Pb-contained solution | Jongjin Kim | SCI |
| Corrosion Science | In situ investigation of the oxidation of Zr-Nb-Cu alloy in high-temperature hydrogenated water | Taeho Kim | SCI |
| Journal of Physical Chemistry C | Zinc Adsorption and Hydration Structures at Yttria-Stabilized Zirconia Surfaces | Binyang Hou | SCI |
| Corrosion Science | Reply to discussion on “Microstructural evolution and stress-corrosion-cracking behavior of thermally aged Ni-Cr-Fe alloy” by S.C. Yoo, K.J. Choi, T. Kim, S.H. Kim, J.Y. Kim, J.H. Kim [Corros. Sci. 111 (2016) 39] | Seung Chang Yoo | SCI |
| Journal of Nuclear Materials | Thermal properties of U-7Mo/Al dispersion fuel | Tae Won Cho | SCI |
| Journal of Nuclear Materials | High-temperature steam oxidation and oxide crack effects of Zr-1Nb-1Sn-0.1Fe fuel cladding | Cheol Min Lee | SCI |
| Journal of Nuclear Materials | Effect of stress evolution on microstructural behavior in U-Mo/Al dispersion fuel | Yong Choi | SCI |
| Nuclear Engineering and Technology | Application of a Dynamic-Nanoindentation Method to Analyze the Local Structure of an Fe-18 at.% Gd Cast Alloy | Gwan Yoon Jeong | SCI |
| Journal of Nuclear Science and Technology | On the Diffusion Coefficient Calculation in Two-step Light Water Reactor Core analysis | Sooyoung Choi | SCI |
| International Journal of Energy Research | New High Performance Light Water Reactor Core Concept with Mixed Cycle Length Operation | Eun Jeong | SCI |
| Journal of Nuclear Science and Technology | Multi-physics steady state analysis of OECD/NEA Modular High Temperature Gas-cooled Reactor MHTGR-350 | Matthieu Lemaire | SCI |
| Computer Physics Communications | On the Transfer Matrix of the Modified Power Method | Peng Zhang | SCI |
| Journal of Computational Physics | A New Approach to Three-Dimensional Neutron Transport Solution Based on the Method of Characteristics and Linear Axial Approximation | Youqi Zheng | SCI |
| Annals of Nuclear Energy | High Accuracy Boronometer Design Developed for Light Water Reactors | Yunki Jo | SCI |
| Journal of Computational Physics | Extension of the Noise Propagation Matrix Method for Higher Mode Solutions | Peng Zhang | SCI |
| Annals of Nuclear Energy | Comparisons of SN and Monte-Carlo Methods in PWR Ex-core Detector Response Simulation | Youqi Zheng | SCI |
| Journal of Computational Physics | Resonance Treatment using Pin-Based Pointwise Energy Slowing-Down Method | Sooyoung Choi | SCI |
| Nuclear Engineering and Technology | Calculation of Degenerated Eigenmodes with Modified Power Method | Peng Zhang | SCI |
| Nuclear Engineering and Technology | Physics Study of Canada Deuterium Uranium Lattice with Coolant Void Reactivity Analysis | Jinsu Park | SCI |
| Annals of Nuclear Energy | Extension of Double Heterogeneity Treatment Method for Coated TRISO fuel particles | Hanjoo Kim | SCI |
| International Journal of Energy Research | Design Study of Long-Life Small Modular Sodium-Cooled Fast Reactor | Jinsu Park | SCI |
| Journal of Nuclear Materials | Texture evolution during annealing of hot extruded U-10wt%Zr alloy by in situ neutron diffraction | S. Irukuvarghula | SCI |
| 논문구분 | 학술지명 | 논문명 | 주저자명 | 공동저자명 | SCI(E) |
| 01 | Journal of Nuclear Materials | Pore growth in U-Mo/Al dispersion fuel | Yeon Soo Kim | G.Y. Jeong, D.-S. Sohn, L.M. Jamison | SCI |
| 01 | Energy | Environmental Life Cycle Risk Modeling of Nuclear Waste Recycling Systems | Sungyeol Choi | Hyo On Nam; Won Il Ko | SCI |
| 01 | Energy Policy | Economic Potential of Fuel Recycling Options: A Lifecycle Cost Analysis of Future Nuclear System Transition in China | Ruxing Gao | Sungyeol Choi; Won Il Ko; Sungki Kim | SCI |
| 01 | Journal of Power Sources | Corrosion Behavior of Surface Treated Steel in Liquid Sodium Negative Electrode of Liquid Metal Battery | Jeonghyeon Lee | Sang Hun Shin; Jung Ki Lee; Sungyeol Choi; Ji Hyun Kim | SCI |
| 01 | Nonproliferation Review | Effects of Nuclear Technology Export Competition on Nuclear Nonproliferation | Sungyeol Choi | Il Soon Hwang | SCI(E) |
| 01 | Nuclear Engineering and Technology | An Integrated Multi-criteria Decision-making Approach for Evaluating Nuclear Fuel Cycle Systems for Long-term Sustainability on the Basis of an Equilibrium Model | Saerom Yoon | Sungyeol Choi; Won Il Ko | SCI |
| 01 | Energy Sources, Part B: Economics, Planning, and Policy | Multinational Planning of Nuclear Energy Systems in Asia | Hyunyub Noh | Sungyeol Choi; Il Soon Hwang | SCI |
| 01 | CORROSION SCIENCE | Mechanism of corrosion of 9Cr and 12Cr ferritic/martensitic steels under oxygen-saturated sodium | Shin Sang Hun | SCI | |
| 01 | PHYSICA STATUS SOLIDI A-APPLICATIONS AND MATERIALS SCIENCE | Modeling of radiation-induced sink evolution in 6061 aluminum alloy in nuclear reactors | Choi, Sang Il | SCI | |
| 01 | JOURNAL OF MECHANICAL SCIENCE AND TECHNOLOGY | Effects of thermal aging and stress triaxiality on PWSCC initiation susceptibility of nickel-based Alloy 600 | Yoo, Seung Chang | SCI | |
| 01 | CORROSION SCIENCE | Microstructural evolution and stress-corrosion-cracking behavior of thermally aged Ni-Cr-Fe alloy | Yoo, Seung Chang | SCI | |
| 01 | JOURNAL OF NUCLEAR MATERIALS | Crack growth behavior of warm-rolled 316L austenitic stainless steel in high-temperature hydrogenated water | Choi, Kyoung Joon | SCI | |
| 01 | SCIENTIFIC REPORTS | The Hydration Structure at Yttria-Stabilized Cubic Zirconia (110)-Water Interface with Sub-Ångström Resolution | Hou, Binyang | SCI | |
| 01 | JOURNAL OF NUCLEAR MATERIALS | Fusion boundary precipitation in thermally aged dissimilar metal welds studied by atom probe tomography and nanoindentation | Choi, Kyoung Joon | SCI | |
| 01 | INTERNATIONAL JOURNAL OF ENERGY RESEARCH | Enhancement of energy performance in betavoltaic cells by optimizing self-absorption of beta particles | Kim, Taeho | SCI | |
| 01 | JOURNAL OF POWER SOURCES | Corrosion Behavior of Surface Treated Steel in Liquid Sodium Negative Electrode of Liquid Metal Battery | Lee, Jeonghyeon | SCI | |
| 01 | CORROSION SCIENCE | Effects of dissolved hydrogen on the crack-initiation and oxidation behavior of nickel-based alloys in high-temperature water | Kim, Taeho | SCI | |
| 01 | Applied Thermal Engineering | Experimental study on a novel liquid metal fin concept preventing boiling critical heat flux for advanced nuclear power reactors | Park, Seong Dae | SCI | |
| 01 | Applied Thermal Engineering | Hybrid Heat Pipe Based Passive Cooling Device for Spent Nuclear Fuel Dry Storage Cask | Yeong Shin Jeong | In Cheol Bang | SCI(E) |
| 01 | Applied Thermal Engineering | Comparison of Flooding Limit and Thermal Performance of Annular and Concentric Thermosyphons at Different Fill Ratios | Kyung Mo Kim | In Cheol Bang | SCI(E) |
| 01 | Nuclear Technology | Development of Passive IN-Core Cooling System (PINCs) for Nuclear Safety Using Hybrid Heat Pipe | Kyung Mo Kim | Yeong Shin Jeong, In Guk Kim, In Cheol Bang | SCI(E) |
| 01 | Annals of Nuclear Energy | Hydrodynamic cavitation characteristics of an orifice system and its effects on CRUD-like SiC deposition | Seong Man Kim | In Cheol Bang | SCI(E) |
| 01 | International Journal of Heat and Mass Transfer | Length effect on entrainment limit of large-L/D vertical heat pipe | Joseph Seo | In Cheol Bang, Jae-Young Lee | SCI |
| 01 | Journal of Alloys and Compounds | High performance all-carbon composite transparent electrodes containing uniform carbon nanotube networks | Hyung Duk Yun | Jinsung Kwak, Se-yang Kim, Han Seo, In Cheol Bang, Sung Yeob Kim, Seoktae Kang, Soon-Yong Kwon | SCI |
| 01 | Applied Thermal Engineering | Experimental Study on a Novel Liquid Metal Fin Concept Preventing Boiling Critical Heat Flux for Advanced Nuclear Power Reactors | Seong Dae Park | Ji Hyun Kim, In Cheol Bang | SCI(E) |