Browse "Dept. of Nuclear and Quantum Engineering(원자력및양자공학과)" by Author Kim, Yonghee
Showing results 186 to 245 of 246
| 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 |
| Physics conditions of passive autonomous frequency control operation in conventional large-size PWRs Abdelhameed, AAE; Lee, Jeong-Ik; Kim, Yonghee, PROGRESS IN NUCLEAR ENERGY, v.118, 2020-01 |
Physics study for high-performance and very-low-boron APR1400 core with 24-month cycle length Do, Manseok; Nguyen, Xuan Ha; Jang, Seongdong; Kim, Yonghee, NUCLEAR ENGINEERING AND TECHNOLOGY, v.52, no.5, pp.869 - 877, 2020-05 |
| Physics study of nuclear reactors for space and rocket propulsions Venneri, Paolo; 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.1761 - 1768, Korean Nuclear Society, 2013-04 |
| Pin-by-Pin Core Calculation with an NEM-Based Two-Level Hybrid CMFD Algorithm Kim, Yonghee; HwanYeal, Yu; Song, Seongho, ANS 2016, ANS 2016, 2016-06-13 |
| Pin-by-Pin core calculation with NEM-based two-level CMFD algorithm = 효율적인 격자단위 노심계산을 위한 NEM 기반 2단계 CMFD 방법론link Song, Seongho; 송성호; et al, 한국과학기술원, 2016 |
| Pin-by-Pin Coupled Transient Monte Carlo Analysis Using the iMC Code Kim, HyeonTae; Kim, Yonghee, FRONTIERS IN ENERGY RESEARCH, v.10, 2022-03 |
| Pin-by-Pin Reactor Core Analysis Based on a NEM-based Two-level Hybrid CMFD Algorithm Song, Seongho; Kim, Yonghee; 유환열, PHYSOR 2016, PHYSOR 2016, 2016-05-02 |
| Pinwise Diffusion Solution of Partially MOX-Loaded PWRs with the GPS (GET PLUS SPH) Method Yu, Hwanyeal; Kim, Jaeha; Kim, Yonghee, NUCLEAR SCIENCE AND ENGINEERING, v.193, no.11, pp.1238 - 1254, 2019-11 |
| Polynomial relaxation in the quasi-static approach and its implementation in nonlinear reactor transient analyses Oh, Tae-suk; Kim, Yonghee, ANNALS OF NUCLEAR ENERGY, v.158, 2021-08 |
| Position-dependency of Fuel Assembly Homogenization in a Pressurized Water Reactor Kim, Yonghee; Heo, Woong, ANS 2016, ANS 2016, 2016-06-13 |
| Possible power increase in a natural circulation Soluble-Boron-Free Small Modular Reactor using the Truly Optimized PWR lattice Wijaya, Steven; Nguyen, Xuan Ha; Kim, Yonghee, NUCLEAR ENGINEERING AND TECHNOLOGY, v.55, no.1, pp.330 - 338, 2023-01 |
| Potential of FAST (floating absorber for safety at transient) as a solution for positive coolant temperature coefficient in sodium-cooled FAST reactors Kim, Chihyung; Kim, Yonghee, ANNALS OF NUCLEAR ENERGY, v.137, 2020-03 |
| Preliminary conceptual design of a new moderated reactor utilizing an LEU fuel for space nuclear thermal propulsion Nam, Seung Hyun; Venneri, Paolo; Kim, Yonghee; Chang, Soon Heung; Jeong, Yong Hoon, PROGRESS IN NUCLEAR ENERGY, v.91, pp.183 - 207, 2016-08 |
| Preliminary design of a helium cooled molten lithium test blanket module for the ITER test in Korea Lee, Dong Won; Hong, Bong Geun; Kim, Yonghee; In, Wang Ki; Yoon, Kyung Ho, FUSION ENGINEERING AND DESIGN, v.82, no.4, pp.381 - 388, 2007-06 |
| Preliminary study of the conceptual design of the Atom Safety System Seo, Gwang Hyoek; Shin, Doyoung; Son, Hong Hyun; Kim, Sung Joong; Kim, Yonghee; Lee, Jeong-Ik, 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2017, Association for Computing Machinery, Inc, 2017-09 |
| Preliminary study ofthe impactof xe-135m on the pcr of candu Kimand, Jaeha; Kim, Yonghee, 2014 International Conference on Physics of Reactors, PHYSOR 2014, Japan Atomic Energy Agency, JAEA, 2014-09 |
| Reactivity Control of a Soluble-Boron-Free 모드슈크리빈야야; Kim, Yonghee, Nuclear Science and Technology Symposium, Nuclear Science and Technology Symposium, 2016-02-03 |
| Real variance analysis of unbiased ratio estimator in Monte Carlo k-eigenvalue calculation Kim, HyeonTae; Jo, YuGwon; Kim, Yonghee, 2019 Transactions of the American Nuclear Society, ANS 2019, pp.860 - 863, American Nuclear Society, 2019-06 |
| Real variance estimation in iDTMC-based depletion analysis Kim, Inyup; Kim, Yonghee, NUCLEAR ENGINEERING AND TECHNOLOGY, v.55, no.11, pp.4228 - 4237, 2023-11 |
| Real Variance Estimation in Monte Carlo Criticality Calculation Accelerated by p-CMFD Feedback Using Spectral Analysis Method Kim, HyeonTae; Jo, YuGwon; Kim, Yonghee, NUCLEAR SCIENCE AND ENGINEERING, v.194, no.4, pp.297 - 307, 2020-04 |
| Real variance estimation of local tallies using spectral analysis method in p-CMFD assisted Monte Carlo criticallity calculation Kim, HyeonTae; Jo, YuGwon; Kim, Yonghee, 2019 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019, pp.120 - 129, American Nuclear Society, 2019-08 |
| Relaxation of quasi-static approach via polynomial interpolation in the predictor corrector quasi-static method Oh, TS; Kim, Yonghee, Transactions of the American Nuclear Society, ANS 2020, pp.734 - 737, American Nuclear Society, 2020-06 |
| Renormalization of power and burnup independent shape annealing function for excore detectors Park, Moon-Ghu; Shin, Ho-Cheol; Choi, Yu-Sun; Park, Dong-Hwan; Kim, Yonghee, ANNALS OF NUCLEAR ENERGY, v.36, no.11-12, pp.1753 - 1759, 2009-12 |
| Review of manufacturing technologies for coated accident tolerant fuel cladding Ko, Jaehwan; Kim, Jong Woo; Min, Hyeong Woo; Kim, Yonghee; Yoon, Young Soo, JOURNAL OF NUCLEAR MATERIALS, v.561, 2022-04 |
| Safety analyses of Kaist Micro modular reactor with modified Gamma+ code Oh, Bong-seong; Lee, Jeong-Ik; Kim, Seong Gu; Yu, Hwanyeal; Moon, Jangsik; Kim, Yonghee; Jeong, Yong Hoon, 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2017, Association for Computing Machinery, Inc, 2017-09 |
| Safety evaluation of supercritical CO2 cooled micro modular reactor Oh, Bong Seong; Ahn, Yoon Han; Yu, Hwanyeal; Moon, Jangsik; Kim, Seong Gu; Cho, Seong Kuk; Kim, Yonghee; et al, ANNALS OF NUCLEAR ENERGY, v.110, pp.1202 - 1216, 2017-12 |
| Safety Improvement with Er Burnable Absorber in CANDU Reactor Loaded with Recovered Uranium Fuel MOHAMMAD ABDUL; Kim, Yonghee; Kim, Woosong, International Workshop on PHWR Challenging Issue for Safe Operation and Long-term Sustainability (CANSAS), International Workshop on PHWR Challenging Issue for Safe Operation and Long-term Sustainability (CANSAS), 2016-10-12 |
| SMART with Trans-Critical CO2 power conversion system for maritime propulsion in Northern Sea Route, part 1: System design Oh, Bong Seong; Kim, Yonghee; Kim, Sung Joong; Lee, Jeong Ik, ANNALS OF NUCLEAR ENERGY, v.149, pp.107792, 2020-12 |
| SMART with trans-critical CO2 power conversion system for maritime propulsion in Northern Sea Route, part 2: Transient analysis Oh, Bong Seong; Kim, Sung Joong; Kim, Yonghee; Lee, Jeong-Ik, ANNALS OF NUCLEAR ENERGY, v.150, pp.107875, 2021-01 |
| Strategic analysis on sizing of flooding valve for successful accident management of small modular reactor An, Hyo Jun; Park, Jae Hyung; Song, Chang Hyun; Lee, Jeong-Ik; Kim, Yonghee; Kim, Sung Joong, Nuclear Engineering and Technology, v.56, no.3, pp.949 - 958, 2024-03 |
| Study of 2-D/1-D fusion method with partial current-based coarse mesh finite difference acceleration for 3-D whole-core transport calculation = 3차원 전노심 수송계산을 위한 부분중성자류 소격격자 유한차분 가속방법이 적용된 2-D/1-D 융합방법 연구link Yuk, Seungsu; 육승수; Kim, Yonghee; 김용희; et al, 한국과학기술원, 2017 |
| Study of steady-state and time-dependent Monte Carlo neutron transport coupled multi-physics reactor analysis in the iMC code = 정상상태 및 과도상태 몬테칼로 중성자 수송과 원자로 다물리 연계 해석 연구 및 iMC 코드 개발link Kim, HyeonTae; Kim, Yonghee; et al, 한국과학기술원, 2022 |
| Study of structural stability at high temperature of pseudo-single tube with double layer as an alternative method for accident-tolerant fuel cladding Kim, Jong Woo; Min, Hyeong Woo; Ko, Jaehwan; Kim, Yonghee; Yoon, Young Soo, JOURNAL OF NUCLEAR MATERIALS, v.566, 2022-08 |
| SYSTEM DESIGN AND ANALYSIS OF A 900-MW(thermal) LEAD-COOLED FAST REACTOR Kim, SJ; Kim, Yonghee; Hong, S; Cho, CH; Eoh, JH; Kim, JB; Wi, MH; et al, NUCLEAR TECHNOLOGY, v.170, no.1, pp.148 - 158, 2010-04 |
| System Design of a Supercritical CO2 cooled Micro Modular Reactor Kim, Seong Gu; Cho, Seong Kuk; HwanYeal, Yu; Kim, Yonghee; Jeong, Yong Hoon; Lee, Jeong-Ik, HTR 2014, Institute of Nuclear and New Energy Technology (INET), Tsinghua University, 2014-10 |
| The application of disk-type burnable absorber in the soluble-boron-free ATOM core Nguyen, Xuan Ha; Jang, Seongdong; Kim, Yonghee, Transactions of the American Nuclear Society, ANS 2020, pp.651 - 654, American Nuclear Society, 2020-06 |
| Theoretical Study on the Estimation of Nuclear Resonance Fluorescence Cross Sections = 핵공명형광(NRF) 반응단면적의 이론적 평가 방법 연구link Ju, Kwangho; Kim, Yonghee; et al, 한국과학기술원, 2019 |
| Thermo-fluid investigation on a double-side-cooled annular fuel for the prismatic very high temperature gas-cooled reactor Tak, Nam-Il; Kim, Yonghee; Choi, Jae-Hyuk; Lee, Won Jae, NUCLEAR ENGINEERING AND DESIGN, v.238, no.10, pp.2821 - 2827, 2008-10 |
| Three-D core multiphysics for simulating passively autonomous power maneuvering in soluble-boron-free SMR with helical steam generator Abdelhameed, Ahmed Amin E.; Chaudri, Khurrum Saleem; Kim, Yonghee, NUCLEAR ENGINEERING AND TECHNOLOGY, v.52, no.12, pp.2699 - 2708, 2020-12 |
| Three-dimensional simulation of passive frequency regulations in the soluble-boron-free SMR ATOM Abdelhameed, Ahmed Amin E.; Kim, Yonghee, NUCLEAR ENGINEERING AND DESIGN, v.361, 2020-05 |
| TRU self-recycling in a high temperature modular helium reactor Jo, Chang Keun; Kim, Yonghee; Noh, Jae Man; Venneri, Francesco, NUCLEAR ENGINEERING AND DESIGN, v.242, pp.215 - 220, 2012-01 |
| Truly-optimized PWR lattice for innovative soluble-boron-free small modular reactor Nguyen, Xuan Ha; Jang, Seongdong; Kim, Yonghee, SCIENTIFIC REPORTS, v.11, no.1, 2021-06 |
| Two-step pin-by-pin reactor depletion method based on the GET Plus SPH (GPS) leakage correction = GPS 중성자 누설 보정법에 기초한 2단계 봉단위 원자로심 연소계산 방법론link Jeong, Hae Sun; Kim, Yonghee; et al, 한국과학기술원, 2023 |
| Uncertainty quantification of the early Deterministic Truncation of <onte Carlo (DTMC) solutions = DTMC 방법론의 초기 활성주기 원자로 인자 불확실도 평가link Kim, HyeonTae; Kim, Yonghee; et al, 한국과학기술원, 2018 |
| Unstructured Mesh-Based Neutronics and Thermomechanics Coupled Steady-State Analysis on Advanced Three-Dimensional Fuel Elements with Monte Carlo Code iMC Kim, HyeonTae; Kim, Yonghee, NUCLEAR SCIENCE AND ENGINEERING, v.195, no.5, pp.464 - 477, 2021-05 |
| Unstructured mesh-grid multi-physics analysis with Monte Carlo iMC code for advanced fuel elements Kim, HyeonTae; Kim, Yonghee, Transactions of the American Nuclear Society, ANS 2020, pp.738 - 741, American Nuclear Society, 2020-06 |
| Uranium Enrichment Reduction in the Prototype Gen-IV Sodium-Cooled Fast Reactor (PGSFR) with PBO Reflector Kim, Chihyung; Hartanto, Donny; Kim, Yonghee, NUCLEAR ENGINEERING AND TECHNOLOGY, v.48, no.2, pp.351 - 359, 2016-04 |
| Use of Er Burnable Absorber for Improvement of CANDU6 Safety Parameters Motalab, Mohammad Abdul; Kim, Woosong; Kim, Yonghee, NUCLEAR TECHNOLOGY, v.201, no.2, pp.122 - 137, 2018-01 |
| Use of Quasi-Monoenergetic Laser Compton Scattering Beam for Enhanced Transmutation of Nuclear Waste Kim, Yonghee; HASEEB UR; Lee, Jiyoung, PHYSOR 2016, PHYSOR 2016, 2016-05-02 |
| Whole core transport analysis with the DTMC method in a small modular reactor Kim, Inhyung; Kim, Yonghee, 2018 Transactions of the American Nuclear Society, ANS 2018, pp.612 - 615, American Nuclear Society, 2018-11 |
| Whole-core depletion calculation using domain decomposed continuous-energy Monte Carlo simulation via McBOX with p-CMFD acceleration and inline feedback Jo, YuGwon; Kim, HyeonTae; Kim, Yonghee; Cho, Nam Zin, ANNALS OF NUCLEAR ENERGY, v.139, 2020-05 |
| Xe-135m impact on the PCR measurement of CANDU6 core Kim, Jaeha; Kim, Yonghee, 2015 ANS Annual Meeting, pp.682 - 684, American Nuclear Society, 2015-06 |
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