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이덕중
Lee, Deokjung

이덕중

Department of Nuclear Engineering(원자력공학과)

  • Computational Reactor physics & Experiment Lab.
  • Website
Research Interests
reactor physics;nuclear reactor physics;neutron transport theory;neutron diffusion theory;code development;method development;advanced reactor design;high-performance computing;reactor core simulator;중성자 수송이론;중성자 확산이론;원자로 물리학;코드 개발;고성능 컴퓨팅;원자로 노심 시뮬레이터;첨단 원자로 설계;방법 개발
Lab Description
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.
Researcher ID Research Gate ORCiD Scopus Google Scholar
Previous
Development and validation of isotope prediction module for VVER spent nuclear fuel analysis File

Jang, Jaerim , Lee, Deokjung

Article Issue Date2024-05 View14
Uncertainty Analysis of UAM TMI-1 Benchmark by STREAM/RAST-K File File

Jang, Jaerim , Jo, Yunki , Lee, Deokjung

Article Issue Date2024-05 View25
High-Fidelity Transient Analysis with STREAM Based on the Predictor-Corrector Quasi-Static Method File

Rahman, Anisur , Lee, Hyun Chul , Lee, Deokjung

Article Issue Date2024-03 View19
Modelling Atomic Relaxation and Bremsstrahlung in the Deterministic Code STREAM File File

Mai, Nhan Nguyen Trong , Kim, Kyeongwon , Lee, Deokjung

Article Issue Date2024-02 View19
Inverted fuel geometry implementation for a fast reactor: Potential improvements in neutronic and thermalhydraulic performance File

Khandaq, Muhammad Farid , Lee, Deokjung

Article Issue Date2024-01 View17
Development of Multiphysics Framework to Analyze Dynamic Gap Heat Transfer and Cross-Flow Effect on Partial Rod Ejection Accident File

Zahur, Awais , Ali, Muhammad Rizwan , Lee, Deokjung

Article Issue Date2023-12 View22
Effect of two way thermal hydraulic-fuel performance coupling on multicycle depletion File File

Zahur, Awais , Ali, Muhammad Rizwan , Lee, Deokjung

Article Issue Date2023-12 View19
CEFR control rod drop transient simulation using RAST-F code system File File

Tuan, Quoc Tran , Huo, Xingkai , Fridman, Emil , Lee, Deokjung

Article Issue Date2023-12 View12
Coupled neutronics/thermal-hydraulic analysis of ANTS-100e using MCS/RAST-F two-step code system File

Nguyen, Tung Dong Cao , Tran, Tuan Quoc , Lee, Deokjung

Article Issue Date2023-11 View27
High fidelity transient solver in STREAM based on multigroup coarse-mesh finite difference method File

Rahman, Anisur , Lee, Hyun Chul , Lee, Deokjung

Article Issue Date2023-09 View12
Development of an artificial neural network model for generating macroscopic cross-sections for RAST-AI File

Dzianisau, Siarhei , Saeju, Korawit , Lee, Hyun Chul , Lee, Deokjung

Article Issue Date2023-06 View15
Group constants generation by Monte Carlo code MCS for LWR analysis File

Nguyen, Trung Dong Cao , Lee, Deokjung

Article Issue Date2023-04 View12
On-the-fly energy release per fission model in STREAM with explicit neutron and photon heating File File

Mai, Nhan Nguyen Trong , Lee, Woonghee , Kim, Kyeongwon , Ebiwonjumi, Bamidele , Kim, Wonkyeong , Lee, Deokjung

Article Issue Date2023-03 View21
Development of angle-dependent linear source approximation for three-dimensional method of characteristics transport analysis method in STREAM File

Choe, Jiwon , Lee, Deokjung

Article Issue Date2023-02 View12
Performance analysis of nuclear reactor core loaded with Accident-Tolerant Fuel: Mo/Cr metallic microcell UO(2 )pellets and CrAl coating File

Jeong, Eun , Jo, Yunki , Shin, ChangHwan , Yang, Yong-Sik , Kim, Jae-Yong , Lee, Deokjung

Article Issue Date2022-09 View16
Validation of MCS code for shielding calculation using SINBAD File File

Feng, XiaoYong , Zhang, Peng , Lee, Hyunsuk , Lee, Deokjung , Lee, Hyun Chul

Article Issue Date2022-09 View19
Development of nodal diffusion code RAST-V for Vodo-Vodyanoi Energetichesky reactor analysis File File

Jang, Jaerim , Dzianisau, Siarhei , Lee, Deokjung

Article Issue Date2022-09 View18
Incorporation of anisotropic scattering into the method of characteristics File File

Rahman, Anisur , Lee, Deokjung

Article Issue Date2022-09 View18
Propagation of radiation source uncertainties in spent fuel cask shielding calculations File File

Ebiwonjumi, Bamidele , Mai, Nhan Nguyen Trong , Lee, Hyun Chul , Lee, Deokjung

Article Issue Date2022-08 View18
A novel S-N/MOC collaborative method for few-group cross-section generation with versatile neutron spectral adaptability in advanced reactor physics analysis File

Wei, Linfang , Lee, Deokjung , Lee, Hyun Chul

Article Issue Date2022-07 View23
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