Browse "NE-Journal Papers(저널논문)" by Author Kim, Yonghee
Showing results 1 to 60 of 108
| A Comparative Physics Study for an Innovative Sodium-Cooled Fast Reactor (iSFR) Hartanto, Donny; Kim, Chihyung; Kim, Yonghee, INTERNATIONAL JOURNAL OF ENERGY RESEARCH, v.42, no.1, pp.151 - 162, 2018-01 |
| A concept design of supercritical CO2 cooled SMR operating at isolated microgrid region Kim, Seong Gu; Yu, HwanYeal; Moon, Jangsik; Baik, Seungjoon; Kim, Yonghee; Jeong, Yong Hoon; Lee, Jeong-Ik, INTERNATIONAL JOURNAL OF ENERGY RESEARCH, v.41, no.4, pp.512 - 525, 2017-03 |
A Conceptual Study of a Supercritical CO2-Cooled Micro Modular Reactor Yu, HwanYeal; Hartanto, Donny; Moon, Jangsik; Kim, Yonghee, ENERGIES, v.8, no.12, pp.13938 - 13952, 2015-12 |
| A feasibility study on low enriched uranium fuel for nuclear thermal rockets - II: Rocket and reactor performance Venneri, Paolo F; Kim, Yonghee, PROGRESS IN NUCLEAR ENERGY, v.87, pp.156 - 167, 2016-03 |
| A feasibility study on photo-production of Tc-99m with the nuclear resonance fluorescence Ju, Kwangho; Lee, Jiyoung; Rehman, Haseeb Ur; Kim, Yonghee, NUCLEAR ENGINEERING AND TECHNOLOGY, v.51, no.1, pp.176 - 189, 2019-02 |
| A Feasibility Study on the Transmutation of 100Mo to 99mTc with Laser-Compton Scattering Photons Lee, Jiyoung; Rehman, Haseeb Ur; Kim, Yonghee, NUCLEAR TECHNOLOGY, v.201, no.1, pp.41 - 51, 2018-01 |
| A Lattice-Based Monte Carlo Evaluation of Canada Deuterium Uranium-6 Safety Parameters Kim, Yonghee; Hartanto, Donny; Kim, Woosong, NUCLEAR ENGINEERING AND TECHNOLOGY, v.48, no.3, pp.642 - 649, 2016-06 |
| A leakage correction with burnup-dependent GPS method in two-step core depletion analysis Jeong, Hae Sun; Oh, Taesuk; Kim, Yonghee, ANNALS OF NUCLEAR ENERGY, v.183, 2023-04 |
| A leakage correction with SPH factors for two-group constants in GET-based pin-by-pin reactor analyses Yu, Hwan Yeal; Kim, Woosong; Kim, Yonghee, ANNALS OF NUCLEAR ENERGY, v.129, pp.30 - 55, 2019-07 |
| A neutronic feasibility study on Be-free He-cooled solid breeder blanket Han, B; Kim, Yonghee; Hong, BG; Kim, CH, FUSION ENGINEERING AND DESIGN, v.81, no.1-7, pp.725 - 728, 2006-02 |
| A neutronic investigation of He-cooled liquid Li-breeder blankets for fusion power reactor Kim, Yonghee; Hong, BG; Kim, CH, FUSION ENGINEERING AND DESIGN, v.75-79, pp.1067 - 1070, 2005-11 |
| A new approach for uncertainty quantification in predictor-corrector quasi-static Monte Carlo transient simulation Oh, Taesuk; Kim, Inyup; Kim, Yonghee, FRONTIERS IN ENERGY RESEARCH, v.11, 2023-01 |
| A New Embedded Analysis with Pinwise Discontinuity Factors for Pin Power Reconstruction Yu, Hwanyeal; Jang, Seongdong; Kim, Yonghee, NUCLEAR SCIENCE AND ENGINEERING, v.195, no.7, pp.766 - 777, 2021-07 |
| A New Two-Step Methodology for CANDU Analysis with the APEC-Assisted Nodal Equivalence Theory Motalab, Mohammad Abdul; Kim, Woosong; Kim, Yonghee, NUCLEAR TECHNOLOGY, v.205, no.9, pp.1185 - 1204, 2019-02 |
| A nodal and finite difference hybrid method for pin-by-pin heterogeneous three-dimensional light water reactor diffusion calculations Lee, DJ; Downar, TJ; Kim, Yonghee, NUCLEAR SCIENCE AND ENGINEERING, v.146, no.3, pp.319 - 339, 2004-03 |
| A Reduced-Boron OPR1000 Core Based on the BigT Burnable Absorber Yu, Hwanyeal; Yahya, Mohd Syukri; Kim, Yonghee, NUCLEAR ENGINEERING AND TECHNOLOGY, v.48, no.2, pp.318 - 329, 2016-04 |
| A study of the behavior of the floating absorber for safety at transient(FAST) in an innovative sodium-cooled fast reactor (iSFR) Lee, Seongmin; Kim, Yonghee; Choi, Yonadan; Jeong, Yong Hoon, ANNALS OF NUCLEAR ENERGY, v.179, 2022-12 |
| A Study on Reconstruction of Intrapin Power Distribution in Pinwise Two-Group Diffusion Analysis Nguyen, Xuan Ha; Kim, Yonghee, NUCLEAR SCIENCE AND ENGINEERING, v.189, no.3, pp.224 - 242, 2018-04 |
| A Study on the Optimal Position for the Secondary Neutron Source in Pressurized Water Reactors Sun, Jungwon; Yahya, Mohd Syukri; Kim, Yonghee, NUCLEAR ENGINEERING AND TECHNOLOGY, v.48, no.6, pp.1291 - 1302, 2016-12 |
| Advancements in the Development of Low Enriched Uranium Nuclear Thermal Rockets Paolo Venneri; Kim, Yonghee, Energy Procedia, v.131, pp.53 - 60, 2017-11 |
| An advanced core design for a soluble-boron-free small modular reactor ATOM with centrally-shielded burnable absorber Nguyen, Xuan Ha; Kim, Chihyung; Kim, Yonghee, NUCLEAR ENGINEERING AND TECHNOLOGY, v.51, no.2, pp.369 - 376, 2019-04 |
| An iDTMC-based Monte Carlo depletion of a 3D SMR with intra-pin flux renormalization Kim, Inhyung; Kim, Inyup; Kim, Yonghee, FRONTIERS IN ENERGY RESEARCH, v.10, 2022-08 |
| An improved deterministic truncation of Monte Carlo solution for pin-resolved nuclear reactor analysis Kim, Inhyung; Kim, Yonghee, ANNALS OF NUCLEAR ENERGY, v.166, 2022-02 |
| An innovative core design for a soluble-boron-free small pressurized water reactor Yahya, Mohd Syukri; Kim, Yonghee, INTERNATIONAL JOURNAL OF ENERGY RESEARCH, v.42, no.1, pp.73 - 81, 2018-01 |
| An LEU-loaded long-life innovative sodium-cooled fast reactor (iSFR) with novel and passive safety devices Hartanto, Donny; Kim, Inhyung; Kim, Chihyung; Kim, Yonghee, ANNALS OF NUCLEAR ENERGY, v.95, pp.86 - 101, 2016-09 |
| An optimization study on the excess reactivity in a linear breed-and-burn fast reactor (B&BR) Hartanto, Donny; Kim, Chihyung; Kim, Yonghee, ANNALS OF NUCLEAR ENERGY, v.94, pp.62 - 71, 2016-08 |
| Analysis on short-term decay heat after shutdown during load-follow operation with seasonal and daily scenarios Hwang, Dae Hee; Kim, Yonghee, NUCLEAR ENGINEERING AND TECHNOLOGY, v.54, no.10, pp.3878 - 3887, 2022-10 |
| Applicability of Swaging as an Alternative for the Fabrication of Accident-Tolerant Fuel Cladding Kim, Dae Yun; Lee, You Na; Kim, Joon Han; Kim, Yonghee; Yoon, Young Soo, ENERGIES, v.13, no.12, 2020-06 |
| Basic concepts of DEMO and a design of a helium-cooled molten lithium blanket for a testing in ITER Hong, Bong Geun; Lee, Dong Won; Wang, Son Jong; Kim, Yonghee; In, Wang Ki; Yoon, Kyung Ho, FUSION ENGINEERING AND DESIGN, v.82, no.15-24, pp.2399 - 2405, 2007-10 |
| Burnable absorber-integrated Guide Thimble (BigT) - I: design concepts and neutronic characterization on the fuel assembly benchmarks Yahya, Mohd Syukri; Yu, Hwanyeol; Kim, Yonghee, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, v.53, no.7, pp.1048 - 1060, 2016 |
| Burnable absorber-integrated guide thimble (BigT) - II: application to 3D PWR core design Yahya, Mohd Syukri; Kim, Yonghee, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, v.53, no.10, pp.1521 - 1527, 2016 |
| Burnable poison for reactivity management in a very high temperature reactor Jo, Chang Keun; Kim, Yonghee; Noh, Jae Man, ANNALS OF NUCLEAR ENERGY, v.36, no.3, pp.298 - 304, 2009-04 |
| Characterization of a sodium-cooled fast reactor in an MHR-SFR synergy for TRU transmutation Hong, Ser Gi; Kim, Yonghee; Venneri, Francesco, ANNALS OF NUCLEAR ENERGY, v.35, no.8, pp.1461 - 1470, 2008-08 |
| Comparison of the Laser-Compton scattering and the conventional bremsstrahlung X-rays for photonuclear transmutation Rehman, Haseeb Ur; Lee, Jiyoung; Kim, Yonghee, INTERNATIONAL JOURNAL OF HYDROGEN ENERGY, v.42, no.1, pp.236 - 244, 2018-01 |
| Conceptual design of reactor system for hybrid micro modular reactor (H-MMR) using potassium heat pipe Choi, Young Jae; Lee, Seongmin; Jang, Seongdong; Son, In Woo; Kim, Yonghee; Lee, Jeong-Ik; Jeong, Yong Hoon, NUCLEAR ENGINEERING AND DESIGN, v.370, 2020-12 |
| Convergence analysis of the nonlinear coarse-mesh finite difference method for one-dimensional fixed-source neutron diffusion problem Lee, DJ; Downar, TJ; Kim, Yonghee, NUCLEAR SCIENCE AND ENGINEERING, v.147, no.2, pp.127 - 147, 2004-06 |
| Convergence Studies on Nonlinear Coarse-Mesh Finite Difference Accelerations for Neutron Transport Analysis Kim, Hyeon Tae; Kim, Yonghee, NUCLEAR SCIENCE AND ENGINEERING, v.191, no.2, pp.136 - 149, 2018-04 |
| Daily Load-Follow Operation in LEU plus -Loaded APR1400 Using Mode-K plus Control Logic Khalefih, Husam; Jeong, Yunseok; Kim, Yonghee, INTERNATIONAL JOURNAL OF ENERGY RESEARCH, v.2023, 2023-10 |
| Design and analysis of HYPER Song, TY; Kim, Yonghee; Lee, BO; Cho, CH, ANNALS OF NUCLEAR ENERGY, v.34, no.11, pp.902 - 909, 2007-11 |
| Deterministic Truncation of the Monte Carlo Transport Solution for Reactor Eigenvalue and Pinwise Power Distribution Kim, Inhyung; Kim, HyeonTae; Kim, Yonghee, NUCLEAR SCIENCE AND ENGINEERING, v.194, no.1, pp.14 - 31, 2020-01 |
| Development and validation of a fast sub-channel code for LWR multi-physics analyses Chaudri, Khurrum Saleem; Kim, Jaeha; Kim, Yonghee, NUCLEAR ENGINEERING AND TECHNOLOGY, v.51, no.5, pp.1218 - 1230, 2019-08 |
| Development and validation of multiphysics PWR core simulator KANT Oh, Taesuk; Jeong, Yunseok; Khale, Husam; Kim, Yonghee, NUCLEAR ENGINEERING AND TECHNOLOGY, v.55, no.6, pp.2230 - 2245, 2023-06 |
| Development of 3-D HCMFD algorithm for efficient pin-by-pin reactor analysis Kim, Jaeha; Kim, Yonghee, ANNALS OF NUCLEAR ENERGY, v.127, pp.87 - 98, 2019-05 |
| Development of a computer code system for the analysis of prism and pebble type VHTR cores Noh, Jae Man; Kim, Kang-Seog; Kim, Yonghee; Lee, Hyun Chul, ANNALS OF NUCLEAR ENERGY, v.35, no.10, pp.1919 - 1928, 2008-10 |
| Development of a tokamak reactor system code and its application for concept development of a demo reactor Hong, Bong Guen; Lee, Dong Won; Kim, Suk-Kwon; Kim, Yonghee, FUSION ENGINEERING AND DESIGN, v.83, no.10-12, pp.1615 - 1618, 2008-12 |
| Diffusion-Based Finite Element Method to Estimate the Reactivity Changes Due to Core Deformation in an SFR Heo, Woong; Kim, Yonghee, NUCLEAR SCIENCE AND ENGINEERING, v.189, no.1, pp.41 - 55, 2018-01 |
| Evaluation of CANDU6 PCR (power coefficient of reactivity) with a 3-D whole-core Monte Carlo Analysis Motalab, Mohammad Abdul; Kim, Woosong; Kim, Yonghee, NUCLEAR ENGINEERING AND DESIGN, v.295, pp.127 - 137, 2015-12 |
| Fabrication of oxide pellets containing lumped Gd2O3 using Y2O3-stabilized ZrO2 for burnable absorber fuel applications Mistarihi, Mistarihi, Qusai; Park, Wooseong; Nam, Kyungseok; Yahya, Mohd-Syukri; Kim, Yonghee; Ryu, Ho Jin, INTERNATIONAL JOURNAL OF ENERGY RESEARCH, v.42, no.6, pp.2141 - 2151, 2018-05 |
| FAST (floating absorber for safety at transient) for the improved safety of sodium-cooled burner fast reactors Kim, Chihyung; Jang, Seongdong; Kim, Yonghee, NUCLEAR ENGINEERING AND TECHNOLOGY, v.53, no.6, pp.1747 - 1755, 2021-06 |
| Feasibility assessment of the alumina-forming duplex stainless steels as accident tolerant fuel cladding materials for light water reactors Kim, Chaewon; Kim, Hyunmyung; Jang, Changheui; Kim, Kangsan; Kim, Yonghee; Lee, Seungjae; Jang, Hun, INTERNATIONAL JOURNAL OF ENERGY RESEARCH, v.44, no.10, pp.8074 - 8088, 2020-08 |
| Feasibility of a novel photoproduction of Ac-225 and Th-227 with natural thorium target Ju, Kwangho; Kim, Yonghee, SCIENTIFIC REPORTS, v.12, no.1, 2022-01 |
| Feasibility of passive autonomous frequency control operation in a Soluble-Boron-Free small PWR Abdelhameed, Ahmed Amin E.; Nguyen, Xuan Ha; Lee, Jeong-Ik; Kim, Yonghee, ANNALS OF NUCLEAR ENERGY, v.116, pp.319 - 333, 2018-06 |
| Functionalization of the Discontinuity Factor in the Albedo-Corrected Parameterized Equivalence Constants (APEC) Method Kim, Woosong; Lee, Kyunghoon; Kim, Yonghee, NUCLEAR SCIENCE AND ENGINEERING, v.192, no.1, pp.1 - 20, 2018-10 |
| Generation of Exact Discontinuity Factors for NEM Calculations with Two-by-Two Division per Fuel Assembly Kim, HyeonTae; Kim, Woosong; Kim, Yonghee, NUCLEAR SCIENCE AND ENGINEERING, v.193, no.5, pp.441 - 452, 2019-06 |
| Impact of new evaluated nuclear data libraries on core characteristics of innovative reactor designs Liem, Peng Hong; Hartanto, Donny; Kim, Yonghee, PROGRESS IN NUCLEAR ENERGY, v.87, pp.74 - 88, 2016-03 |
| Impacts of an ATF cladding on neutronic performances of the soluble-boron-free ATOM core Nguyen, Xuan Ha; Jang, Seongdong; Kim, Yonghee, INTERNATIONAL JOURNAL OF ENERGY RESEARCH, v.44, no.10, pp.8193 - 8207, 2020-08 |
| Impacts of Burnup-Dependent Swelling of Metallic Fuel on the Performance of a Compact Breed-and-Burn Fast Reactor Hartanto, Donny; Heo, Woong; Kim, Chihyung; Kim, Yonghee, NUCLEAR ENGINEERING AND TECHNOLOGY, v.48, no.2, pp.330 - 338, 2016-04 |
| Improved FAST Device for Inherent Safety of Oxide-Fueled Sodium-Cooled Fast Reactors Abdelhameed, Ahmed Amin E.; Kim, Chihyung; Kim, Yonghee, ENERGIES, v.14, no.15, 2021-08 |
| Improved macroscopic depletion in 2-D nodal analysis by 2x2 albedo-corrected parameterized equivalence constants method Jang, Seongdong; Kim, Yonghee, ANNALS OF NUCLEAR ENERGY, v.175, 2022-09 |
| Improved nodal equivalence with leakage-corrected cross sections and discontinuity factors for PWR depletion analysis Lee, Kyunghoon; Kim, Woosong; Kim, Yonghee, NUCLEAR ENGINEERING AND TECHNOLOGY, v.51, no.5, pp.1195 - 1208, 2019-08 |
Discover
Type
- 2,774 Article
Open Access
- 152 OA Article
Date issued
- 463 2020 - 2024
- 1,120 2010 - 2019
- 712 2000 - 2009
- 369 1990 - 1999
- 110 1980 - 1989