Browse "Dept. of Nuclear and Quantum Engineering(원자력및양자공학과)" by Author Kim, Yonghee
Showing results 97 to 156 of 246
| 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 optimization of reactor depletion methodology in Monte Carlo iMC code = 몬테카를로 노심 분석 코드 iMC에서의 연소 방법론 개발 및 최적화link Kim, Inyup; Kim, Yonghee; et al, 한국과학기술원, 2023 |
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 3D finite element methodology for neutron diffusion equations to estimate the reactivity change due to core deformation in sodium-cooled fast reactors = 소듐냉각고속로의 노심 변형에 따른 반응도 변화 평가를 위한 중성자 확산이론 기반 3차원 유한 요소 방법론 개발link Heo, Woong; Kim, Yonghee; et al, 한국과학기술원, 2018 |
| 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 deterministic truncation of Monte Carlo solution for a pin-resolved nuclear reactor analysis = 연료봉 단위 상세 원자로심 분석을 위한 몬테칼로 해법의 결정론적 근사 방법론 개발link Kim, Inhyung; Kim, Yonghee; et al, 한국과학기술원, 2021 |
| 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 |
| Development of albedo-corrected parameterized equivalence constants for macroscopic depletion in coarse-mesh nodal analysis of nuclear reactors = 원자로심 소격격자 거시연소 해석을 위한 중성자 누설이 보정된 소수군 등가인자 방법론 개발link Jang, Seongdong; Kim, Yonghee; et al, 한국과학기술원, 2022 |
| Development of the 900 second specific impulse carbide low enriched uranium nuclear thermal rocket Venneri, Paolo F; Kim, Yonghee; Husemeyer, Peter; Howe, Stephen, 2014 International Conference on Physics of Reactors, PHYSOR 2014, Japan Atomic Energy Agency, JAEA, 2014-09 |
| 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 |
| ERBIA-LOADED CANDU FUEL FOR MINIMIZATION OF THE COOLANT VOID REACTIVITY MOHAMMAD ABDUL; Kim, Yonghee; Kim, Woosong, International Conference on CANDU Fuel, International Conference on CANDU Fuel, 2016-08-16 |
| Erbium Burnable Absorber to Improvement Safety Parameters of CANDU Loaded With Recovered Uranium MOHAMMAD ABDUL; Kim, Yonghee; Kim, Woosong, ICAPP 2017, ANS, 2017-04-28 |
| 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 |
| Extreme performance multibatch research reactor based on simple plate fuel Venneri, Paolo; Kim, Yonghee, 2015 Transactions of the American Nuclear Society, ANS 2015, pp.1067 - 1069, American Nuclear Society, 2015-11 |
| Fabrication of Neutron Absorber Containing Ceramic Composite Pellets by using Microwave Sintering Mistarihi, Qusai; Ryu, Ho Jin; Yahya, Mohd Syukri; Kim, Yonghee, 한국원자력학회 2016 추계학술대회, 한국원자력학회, 2016-10-27 |
| Fabrication of neutron absorber inserted oxide fuel pellet MISTARIHI QUSA; Ryu, Ho Jin; Kim, Yonghee; Yahya, Nigd-Sykuri, 12th Pacific Rim Conference on Ceramic and Glass Technology (PACRIM 12), The American Ceramic society, 2017-05-24 |
| 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 metallic-fuel-loaded sodium-cooled fast reactors Kim, Chihyung; Kim, Yonghee, Transactions of the American Nuclear Society, ANS 2019, pp.1545 - 1548, American Nuclear Society, 2019-11 |
| 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 and parameterization of small-scale low-enriched Uranium nuclear thermal propulsion = 초소형 저농축우라늄 기반 로켓추진용 원자로 타당성 연구link Rawlins, Samantha B.; Kim, Yonghee; et al, 한국과학기술원, 2018 |
| FEASIBILITY ASSESSMENT OF AIR-COOLING SYSTEM AS AN ULTIMATE HEAT SINK OF THE ATOM SYSTEM Shin, Doyoung; Seo, Gwang Hyeok; Na, Min Wook; Kim, Sung Joong; Kim, Yonghee; Lee, Jeongik, 26th International Conference on Nuclear Engineering (ICONE-26), AMER SOC MECHANICAL ENGINEERS, 2018-07 |
| 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 $^{225}$Ac & $^{227}$Th production and fast neutron utilization in a versatile thorium target system = 다목적 토륨 표적 시스템을 활용한 $^{225}$Ac & $^{227}$Th 생산 및 고속 중성자 활용 가능성 고찰link Ju, KwangHo; Kim, Yonghee; et al, 한국과학기술원, 2023 |
| 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 a very-low-boron core design for APR1400 with 24-month cycle length Do, Manseok; Nguyen, Xuan Ha; Kim, Yonghee, 2018 International Conference on Physics of Reactors: Reactor Physics Paving the Way Towards More Efficient Systems, PHYSOR 2018, pp.4048 - 4057, Sociedad Nuclear Mexicana, A.C., 2018-04 |
| Feasibility of Albedo-corrected parameterized equivalence constants for nodal equivalence theory Kim, Woosong; Kim, Yonghee, Mathematics and Computations, Supercomputing in Nuclear Applications and Monte Carlo International Conference, M and C+SNA+MC 2015, pp.3198 - 3208, American Nuclear Society, 2015-04 |
| Feasibility of low thrust, low-enriched uranium nuclear thermal propulsion Rawlins, Samantha; Kim, Yonghee, Nuclear and Emerging Technologies for Space, NETS 2018, pp.349 - 351, American Nuclear Society, 2018-02 |
| 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 |
| Feasibility study of relaxation of quasi-static approach for reactor transient analyses = 원자로심 과도 현상 분석을 위한 준정상 상태 방법론의 보완 고찰link Oh, Tae-suk; Kim, Yonghee; et al, 한국과학기술원, 2020 |
| Feasibility study on LEU-based molten salt and metal reactor for ultramicro miniaturization = 저농축우라늄 기반 초소형 원자로 구현을 위한 용융염-금속 원자로에 대한 연구link Lee, Eunhyug; Kim, Yonghee; et al, 한국과학기술원, 2022 |
| FEM-based Estimation of Reactivity Change due to Core Deformation in SFR Heo, Woong; Kim, Yonghee, International Conference on Mathematics & Computational Methods Applied to Nuclear Science & Engineering, ANS, 2016-04-20 |
| FEM-based Estimation of Reactivity Change due to Core Deformation in SFR Heo, Woong; Kim, Yonghee, International Conference on Mathematics & Computational Methods Applied to Nuclear Science & Engineering, ANS, 2017-04-20 |
| First-order perturbation for uncertainty quantification in the deterministic truncation of Monte Carlo method Kim, HyeonTae; Kim, Inhyung; Kim, Yonghee, Tech 2018 Iron and Steel Technology Conference and Exposition, pp.430 - 432, American Nuclear Society, 2018-06 |
| Full submersion criticality accident for low enriched uranium nuclear thermal rockets Venneri, Paolo; Kim, Yonghee; Husemeyer, Peter; Howe, Stephen, 2014 ANS Winter Meeting and Nuclear Technology Expo, pp.1425 - 1428, American Nuclear Society, 2014-11 |
| Full submersion criticality accident mitigation in the Carbide LEU-NTR Venneri, Paolo F; Kim, Yonghee, 2015 Nuclear and Emerging Technologies for Space, NETS 2015, pp.299 - 306, American Nuclear Society, 2015-02 |
| 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 discontinuity factor modeling for the in-situ APEC leakage correction in nodal analysis Jang, Seongdong; Kim, Yonghee, Transactions of the American Nuclear Society, ANS 2019, pp.1335 - 1338, American Nuclear Society, 2019-11 |
| 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 modelling for the assembly discontinuity factors in the APEC method Kim, Woosong; Kim, Yonghee, 2017 Transactions of the American Nuclear Society, ANS 2017, pp.1093 - 1095, American Nuclear Society, 2017-06 |
| 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 |
| Improvement of CANDU safety parameters by using the CANFLEX fuel Kim, Woosong; Motalab, Mohammad Abdul; Bae, Jun Ho; Kim, Yonghee, ANNALS OF NUCLEAR ENERGY, v.94, pp.793 - 801, 2016-08 |
| Improvement of Nodal Accuracy by Using Albedo-Corrected Parameterized Equivalence Constants Kim, Woosong; Heo, Woong; Kim, Yonghee, NUCLEAR SCIENCE AND ENGINEERING, v.188, no.3, pp.207 - 245, 2017-08 |
| Improvement of safety parameters by using erbium-loaded canflex fuel bundle in the candu reactor Kim, Woosong; Kim, Yonghee, International Congress on Advances in Nuclear Power Plants: Nuclear Power - A Safe and Sustainable Choice for Green Future, ICAPP 2013, Held with the 28th KAIF/KNS Annual Conference, pp.1812 - 1820, Korean Nuclear Society, 2013-04 |
| Improvement of safety parameters in the CANDU reactor using burnable absorber erbium Motalab, Mohammad Abdul; Kim, Woosong; Kim, Yonghee, 37th Annual Conference of the Canadian Nuclear Society and 41st Annual CNS/CNA Student Conference, Canadian Nuclear Society, 2017-06 |
| In-situ corrections of two-group assembly cross-sections and discontinuity factors by the APEC method Kim, Woosong; Kim, Yonghee, Transactions of the American Nuclear Society, ANS 2017, pp.1440 - 1443, American Nuclear Society, 2017-10 |
| INNOVATIVE CONCEPT FOR AN ULTRA-SMALL NUCLEAR THERMAL ROCKET UTILIZING A NEW MODERATED REACTOR Nam, Seung Hyun; Venneri, Paolo; Kim, Yonghee; Lee, Jeong Ik; Chang, Soon Heung; Jeong, Yong Hoon, NUCLEAR ENGINEERING AND TECHNOLOGY, v.47, no.6, pp.678 - 699, 2015-10 |
| Investigation of a lower thrust nuclear thermal propulsion design utilizing low-enriched uranium fuel Rawlins, Samantha; Kim, Yonghee, 2018 International Conference on Physics of Reactors: Reactor Physics Paving the Way Towards More Efficient Systems, PHYSOR 2018, pp.3220 - 3226, Sociedad Nuclear Mexicana, A.C., 2018-04 |
| Investigation of Nodal Numerical Adjoints From CMFD-Based Acceleration Methods Oh, Taesuk; Kim, Yonghee, FRONTIERS IN ENERGY RESEARCH, v.10, 2022-04 |
| LEU plus loaded APR1400 using accident tolerant fuel cladding for 24-month two-batch fuel management scheme Khalefih, Husam; Oh, Taesuk; Jeong, Yunseok; Kim, Yonghee, NUCLEAR ENGINEERING AND TECHNOLOGY, v.55, no.7, pp.2578 - 2590, 2023-07 |
| Long-cycle and high-burnup fuel assembly for the VHTR Kim, Yonghee; Cho, C; Venneri, F, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, v.44, pp.294 - 302, 2007-03 |
| Measurement and Analysis for Determination of PCR of the CANDU6 Core Kim, Jaeha; Motalab, Mohammad Abdul; Kim, Yonghee; Kim, Gwangsoo, Nuclear Technology, v.201, no.2, pp.138 - 154, 2018-01 |
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