Browse "Dept. of Nuclear and Quantum Engineering(원자력및양자공학과)" by Author Kim, Yonghee
Showing results 141 to 200 of 254
| 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 deterministic truncation in predictor-corrector quasi-static Monte Carlo for time-dependent neutron transport simulations = 결정론적 근사 방법론이 고려된 예측자-수정자 준정상 상태 방법론 기반 시간종속 몬테카를로 중성자 수송 시뮬레이션에 관한 연구link Oh, Taesuk; 오태석; et al, 한국과학기술원, 2024 |
| 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 |
| Measurement and analysis for determination of power coefficient of reactivity of an operating CANDU6 Kim, Jaeha; Kim, Yonghee; Kim, Kwangsoo, 35th Annual Conference of the Canadian Nuclear Society and 38th CNS/CNA Student Conference 2015, pp.568 - 579, Canadian Nuclear Society, 2015-05 |
| Micro-scale molten salt & metal reactor for space applications = 우주 응용을 위한 초소형 용융염 액체금속 원자로link Ryu, Jae-Hyun; 류재현; et al, 한국과학기술원, 2024 |
| Monte Carlo-Deterministic Hybrid Analysis for a Soluble-Boron-Free SMR 모드슈크리빈야야; Kim, Yonghee, International Conference on Mathematics & Computational Methods Applied to Nuclear Science & Engineering, ANS, 2017-04-20 |
| Multi-batch core design study for innovative small modular reactor based on centrally-shielded burnable absorber Wijaya, Steven; Nguyen, Xuan Ha; Jeong, Yunseok; Kim, Yonghee, NUCLEAR ENGINEERING AND TECHNOLOGY, v.56, no.3, pp.907 - 915, 2024-03 |
| n Investigation on the Sustainability of a Sodium-Cooled Breed-and-Burn Fast Reactor (B&BR) 김치형; Kim, Yonghee; Donny Hartanto, ANS Winter Meeting, ANS Winter Meeting, 2016-11-09 |
| Neutronic Analysis of an In-core Co-60 Production Method in CANDU6 Reactors Kim, Yonghee; Motalab, Mohammad Abdul; Lyu, Jinqi, International Conference on CANDU Fuel, International Conference on CANDU Fuel, 2016-08-16 |
| Neutronic Feasibility of a Soluble Boron-Free PWR Core Design with the BigT Burnable Absorber Kim, Yonghee; 모드슈크리빈야야, ICAPP 2016, ICAPP 2016, 2016-04-18 |
| Neutronic optimization of the reflector for a soluble-boron-free small modular reactor atom Nguyen, Xuan Ha; Yu, Hwanyeal; Kim, Yonghee, 2018 Transactions of the American Nuclear Society, ANS 2018, pp.1167 - 1170, American Nuclear Society, 2018-11 |
| Neutronics and Transient Analyses of a Supercritical CO2-Cooled Micro Modular Reactor (MMR) Yu, HwanYeal; Donny Hartanto; Oh, Bong-seong; Lee, Jeong-Ik; Kim, Yonghee, Energy Procedia, v.131, pp.21 - 28, 2017-10 |
| Neutronics and Transient Analyses of a Supercritical CO2-cooled Micro Modular Reactor (MMR) Yu, HwanYeal; Hartanto, Donny; Oh, Bong-seong; Lee, Jeong-Ik; Kim, Yonghee, 5th International Symposium on Innovative Nuclear Energy Systems, INES-5 2016, pp.21 - 28, Elsevier Ltd, 2016-11 |
| Neutronics evaluation of a super-deep-burn with TRU Fully Ceramic Microencapsulated (FCM) fuel in CANDU Hartanto, Donny; Kim, Yonghee; Venneri, Francesco, PROGRESS IN NUCLEAR ENERGY, v.83, pp.261 - 269, 2015-08 |
| Neutronics feasibility of simple and dry recycling technologies for a self-sustainable breed-and-burn fast reactor Kim, Chihyung; Hartanto, Donny; Kim, Yonghee, Annals of Nuclear Energy, v.110, pp.847 - 855, 2017-12 |
| Neutronics optimization and characterization of a long-life SCO2-cooled micro modular reactor Kim, Yonghee; Hartanto, Donny; Yu, Hwanyeal, INTERNATIONAL JOURNAL OF ENERGY RESEARCH, v.41, no.7, pp.976 - 984, 2017-06 |
| Neutronics simulation of burnup-dependent swelling of metallic fuel in a linear breed-and-burn fast reactor (B&BR) Hartanto, Donny; Kim, Yonghee, 2015 ANS Annual Meeting, pp.755 - 757, American Nuclear Society, 2015-06 |
| Nodal cross section corrections with the apec method in an SMR core analysis Lee, Kyunghoon; Kim, Woosong; Kim, Yonghee, 2018 International Conference on Physics of Reactors: Reactor Physics Paving the Way Towards More Efficient Systems, PHYSOR 2018, pp.1916 - 1927, Sociedad Nuclear Mexicana, A.C., 2018-04 |
| Nonoverlapping local/global iterative method for three-dimensional time-dependent neutron transport calculations = 3차원 시간의존적 중성자 수송계산을 위한 비중첩 국소영역/전영역 반복계산 방법link Cho, Bumhee; 조범희; et al, 한국과학기술원, 2016 |
| Novel Passive Safety Devices for a Sodium-Cooled Fast Reactor: FAST and SAFE Kim, Yonghee; 김치형; 김인형; Hartanto, Donny, ICAPP 2016, ICAPP 2016, 2016-04-18 |
| Nuclear design study for innovative natural circulation molten salt fast reactor = 혁신적인 자연순환 용융염고속로 노심 핵설계 연구link Aufanni, Nariratri Nur; 아우파니 나리라트리 누르; et al, 한국과학기술원, 2024 |
| Nuclear fuel assembly for a thermal neutron reactor Kim, Yonghee; Kim, Chihyung; Lee, Jeong-Ik |
| Nuclear fuel pellet with central burnable absorber Kim, Yonghee; Ryu, Ho Jin; Mohd Syukri bin Yahya; Qusai Mahmoud Mohammad Mistarihi; Kim, Chihyung |
| Nuclear fuel rod including disk-type burnable absorber Kim, Yonghee; Jang, Seongdong; Xuan Ha Nguyen |
| NUCLEAR FUEL ROD INCLUDING DISK-TYPE BURNABLE ABSORBER Kim, Yonghee; Jang, seongdong; Nguyen, Xuan Ha |
| NUCLEAR FUEL ROD INCLUDING DISK-TYPE BURNABLE ABSORBER Kim, Yonghee; Jang, seongdong; Nguyen, Xuan Ha |
| Nuclear-thermal analysis of coated particle dispersed plate-fuel loaded in a novel research reactor Lee, Yoonhee; Kim, Yonghee; Cho, Nam-Zin, 2015 ANS Annual Meeting, pp.799 - 802, American Nuclear Society, 2015-06 |
| Numerical design of a 20 MW lead-bismuth spallation target with an injection tube Cho, Chungho; Kim, Yonghee; Song, Tae Yung; Lee, Yong-Bum, NUCLEAR ENGINEERING AND DESIGN, v.238, no.1, pp.90 - 101, 2008-01 |
| One-node and two-node hybrid coarse-mesh finite difference algorithm for efficient pin-by-pin core calculation Song, Seongho; Yu, Hwanyeal; Kim, Yonghee, NUCLEAR ENGINEERING AND TECHNOLOGY, v.50, no.3, pp.327 - 339, 2018-04 |
| One-node CMFD formulations for multi-group SP3equations in hexagonal geometry Jang, Seongdong; Kim, Yonghee, International Conference on Physics of Reactors: Reactor Physics Paving the Way Towards More Efficient Systems, PHYSOR 2018, pp.3178 - 3189, Sociedad Nuclear Mexicana, A.C., 2018-04 |
| Optimal configuration of neutron reflector in He-cooled molten Li blanket Han, B; Kim, Yonghee; Kim, CH, FUSION ENGINEERING AND DESIGN, v.81, no.1-7, pp.729 - 732, 2006-02 |
| Optimization of Laser Compton Scattering for Transmutation of Long-Living Fission Products Kim, Yonghee; HASEEB UR; Lee, Jiyoung, 5th International Conference on Nuclear and Renewable Energy Resources (NURER), 5th International Conference on Nuclear and Renewable Energy Resources (NURER), 2016-09-20 |
| Optimization of one-pass transuranic deep burn in a modular helium reactor Kim, Yonghee; Venneri, Francesco, NUCLEAR SCIENCE AND ENGINEERING, v.160, no.1, pp.59 - 74, 2008-09 |
| Optimization of Reactivity Feedbacks for Autonomous Small PWR Kim, Yonghee; ABDELHAMEED AHMED, International Technical Meeting on Small Reactors, International Technical Meeting on Small Reactors, 2016-11-03 |
| Optimization of the laser-Compton scattering spectrum for the transmutation of high-toxicity and long-living nuclear waste Rehman, Haseeb Ur; Lee, Jiyoung; Kim, Yonghee, ANNALS OF NUCLEAR ENERGY, v.105, pp.150 - 160, 2017-07 |
| Passive Reactivity Control of Nuclear Thermal Propulsion Reactors Venneri, Paolo; Eades, Michael; Kim, Yonghee, NUCLEAR TECHNOLOGY, v.197, no.1, pp.64 - 74, 2017-01 |
| Passive Reactivity Control of Nuclear Thermal Propulsion Reactors Venneri, Paolo; Eades, Michael; Kim, Yonghee, NUCLEAR TECHNOLOGY, v.197, no.1, pp.64 - 74, 2017-01 |
| Passive safety device to improve coolant temperature coefficient of reactivity for sodium-cooled fast reactors = 소듐냉각 고속로의 냉각재 반응도 계수 개선을 위한 피동 안전장치 개념 및 타당성 고찰link Kim, Chihyung; Kim, Yonghee; et al, 한국과학기술원, 2019 |
| Performance criterion of an indirect dry air-cooled condenser for small modular reactor based on pressure transition temperature Shin, Doyoung; Na, Min Wook; Lee, Jeong Ik; Kim, Yonghee; Kim, Sung Joong, INTERNATIONAL JOURNAL OF ENERGY RESEARCH, v.43, no.14, pp.8190 - 8203, 2019-11 |
| Photo-transmutation of 100Mo to 99mTc with Laser-Compton Scattering Gamma-ray Lee, Jiyoung; Kim, Yonghee; HASEEB UR, ANS 2016, ANS 2016, 2016-06-13 |
| Photon and neutron hybrid transmutation for radioactive cesium and iodine Rehman, Haseeb Ur; Ju, Kwangho; Kim, Yonghee, ANNALS OF NUCLEAR ENERGY, v.133, pp.527 - 537, 2019-11 |
| Photon and neutron hybrid transmutation of long-living cesium and iodine isotopes = 광자와 중성자를 동시에 활용한 장수명 Cesium 및 Iodine 동위원소 핵변환 연구link Rehman, Haseeb ur; Kim, Yonghee; et al, 한국과학기술원, 2019 |
| Photoproduction of ${99}^mTc$ with Laser-Compton Scattering Gamma-ray = 레이저-콤프튼-산란 감마선을 이용한 의료용 동위원소 ${99}^mTc$ 광생성 연구link Lee, Jiyoung; Kim, Yonghee; et al, 한국과학기술원, 2017 |
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