Faculty Research Profile
Deokjung Lee
학력
· 2003: Ph. D. Nuclear Engineering, Purdue University
· 1995: M. S. Nuclear Engineering, Seoul National University
· 1993: B. S. Nuclear Engineering, Seoul National University
주요 경력
· 2022 - Present: Professor, UNIST
· 2016 - 2021: Associate Professor, UNIST
· 2011 - 2015: Assistant Professor, UNIST
· 2009 - 2011: R&D Staff, Oak Ridge National Laboratory
· 2005 - 2009: Senior Nuclear Engineer, Studsvik Scandpower Inc.,
· 1995 - 2000: Technical Staff, Korea Electric Power Research Institute
수상/학회/외부활동
· 2022: KNS Best Paper Award
· 2020: The minister of the Ministry of Science and ICT (MSIT) Award
· 2018: Doosan Nuclear Technology Award at 2018 KNS Autumn Meeting
· 2017: M&C 2017 Organization Committee
· 2016: PHYSOR 2016 Organization Committee
· 2010 – 2012: Member, Joint Benchmark Committee of Mathematics and Computation, Reactor Physics, and Radiation & Shielding, American Nuclear Society
· 2008 – 2011: Member, Reactor Physics Division Program Committee, American Nuclear Society
전산 노물리 및 실험 연구실
CORE (COmputational and Reactor physics and Experiment)
UNIST CORE (COmputational Reactor physics and Experiment laboratory) is an academic laboratory dedicated to the research in nuclear reactor physics. The laboratory actively develops theoretical methods and computer codes to tackle neutron transport and diffusion theory in all its aspects: collision with medium, slowing-down, scattering, absorption, nuclear fission, chain reaction, secondary particle production and nuclide transmutation. The laboratory manages the knowledge required for reactor core design, analysis and operation and conducts studies in the fields of criticality, reactivity feedback and reactivity control, reactor kinetics, nuclear fuel depletion, perturbation theory, deep-penetration shielding, steady-state and transient simulations, reactor design and safety analysis, and many more.
UNIST CORE (COmputational Reactor physics and Experiment laboratory) is an academic laboratory dedicated to the research in nuclear reactor physics. The laboratory actively develops theoretical methods and computer codes to tackle neutron transport and diffusion theory in all its aspects: collision with medium, slowing-down, scattering, absorption, nuclear fission, chain reaction, secondary particle production and nuclide transmutation. The laboratory manages the knowledge required for reactor core design, analysis and operation and conducts studies in the fields of criticality, reactivity feedback and reactivity control, reactor kinetics, nuclear fuel depletion, perturbation theory, deep-penetration shielding, steady-state and transient simulations, reactor design and safety analysis, and many more.
연구분야
Reactor Physics, Numerical Methods for Transport and Diffusion Analysis, Advanced Reactor Designs and Analysis, High Performance Computing, Lattice Ph
Reactor Physics, Numerical Methods for Transport and Diffusion Analysis, Advanced Reactor Designs and Analysis, High Performance Computing, Lattice Ph
연구 희망분야
MOC transport code, 3D Nodal diffusion code, Monte Carlo code, Reactor design, Fast reactor analysis, Multi-physics coupling, Sensitivity & uncertainty analysis, AI & simulator
MOC transport code, 3D Nodal diffusion code, Monte Carlo code, Reactor design, Fast reactor analysis, Multi-physics coupling, Sensitivity & uncertainty analysis, AI & simulator
연구주제
원자로 물리학, 코드 개발, 방법 개발, 첨단 원자로 설계, 고성능 컴퓨팅, 원자로 노심 시뮬레이터, 소형모듈원자로 설계
Reactor physics, code development, method development, advanced reactor design, high-performance computing, reactor core simulator, SMR(Small Modular Reactor) design
Reactor physics, code development, method development, advanced reactor design, high-performance computing, reactor core simulator, SMR(Small Modular Reactor) design
국가연구개발사업 기술 분류체계
국가과학기술표준분류
EG. 원자력 > EG01. 원자로노심기술 > EG0102. 노심 핵설계 기술
논문
· COMPUTER PHYSICS COMMUNICATIONS / Three-dimensional method of characteristics/diamond-difference transport analysis method in STREAM for whole-core neutron transport calculation / Choi, Sooyoung, Lee, Deokjung / 2021-03
· ANNALS OF NUCLEAR ENERGY / MCS – A Monte Carlo particle transport code for large-scale power reactor analysis / Lee, Hyunsuk; Kim, Wonkyeong; Zhang, Peng; Lemaire, Matthieu; Khassenov, Azamat; Yu, Jiankai; Jo, Yunki; Park, Jinsu; Lee, Deokjung / 2020-05
· NUCLEAR ENGINEERING AND TECHNOLOGY / Verification and validation of STREAM/RAST-K for PWR analysis / Choe, Jiwon; Choi, Sooyoung; Zhang, Peng; Park, Jinsu; Kim, Wonkyeong; Shin, Ho Cheol; Lee, Hwan Soo; Jung, Ji-Eun; Lee, Deokjung / 2019-04
· JOURNAL OF COMPUTATIONAL PHYSICS / Resonance treatment using pin-based pointwise energy slowing-down method / Choi, Sooyoung; Lee, Changho; Lee, Deokjung / 2017-02
특허
· [USA] FUEL ASSEMBLY DESIGN CONCEPT AND MIXED CYCLE SENGTH OPERATION METHOD FOR LONG CYCLE LENGTH PRESSURIZED WATER REACTOR OPERATION / Deokjung Lee, Eun Jeong, Sooyoung Choi, Jinsu Park, Jaerim Jang, Peng Zhang / 2022
· [KOR] HYBRID DEPLETION METHOD FOR LIGHT WATER REACTOR ANALYSIS / Deokjung Lee, Wonkyeong Kim, Sooyoung Choi, Hyunsuk Lee / 2017
· [KOR] APPARATUS AND METHOD FOR REACTOR CORE ANALYSIS USING PSM / Deokjung Lee, Sooyoung Choi / 2017