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Lee, Deokjung (이덕중)

Department
Department of Nuclear Engineering(원자력공학과)
Website
https://sites.google.com/a/unistcore.com/main/
Lab
Computational Reactor physics & Experiment Lab. (원자로물리 연구실)
Research Keywords
중성자 수송이론, 중성자 확산이론, 원자로 물리학, 코드 개발, 고성능 컴퓨팅, 원자로 노심 시뮬레이터, 첨단 원자로 설계, 방법 개발, reactor physics, nuclear reactor physics, neutron transport theory, neutron diffusion theory, code development, method development, advanced reactor design, high-performance computing, reactor core simulator
Research Interests
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.
This table browses all dspace content
Issue DateTitleAuthor(s)TypeViewAltmetrics
2020-12Neutronic simulation of China experimental fast reactor start-up tests- part II: MCS code Monte Carlo calculationTuan Quoc Tran; Choe, Jiwon; Du, Xianan, et alARTICLE10 Neutronic simulation of China experimental fast reactor start-up tests- part II: MCS code Monte Carlo calculation
2020-09Overcoming the challenges of Monte Carlo depletion: Application to a material-testing reactor with the MCS codeDos, Vutheam; Lee, Hyunsuk; Jo, Yunki, et alARTICLE186 Overcoming the challenges of Monte Carlo depletion: Application to a material-testing reactor with the MCS code
2020-09Validation of nuclide depletion capabilities in Monte Carlo code MCSEbiwonjumi, Bamidele; Lee, Hyunsuk; Kim, Wonkyeong, et alARTICLE162 Validation of nuclide depletion capabilities in Monte Carlo code MCS
2020-07Analysis and comparison of direct inversion and Kalman filter methods for self -powered neutron detector compensationKhoshahval, Farrokh; Zhang, Peng; Lee, DeokjungARTICLE40 Analysis and comparison of direct inversion and Kalman filter methods for self -powered neutron detector compensation
2020-07Interpretation of two SINBAD photon-leakage benchmarks with nuclear library ENDF/B-VIII.0 and Monte Carlo code MCSLemaire, Matthieu; Lee, Hyunsuk; Zhang, Peng, et alARTICLE41 Interpretation of two SINBAD photon-leakage benchmarks with nuclear library ENDF/B-VIII.0 and Monte Carlo code MCS
2020-06Coupling of FRAPCON for fuel performance analysis in the Monte Carlo code MCSYu, Jiankai; Lee, Hyunsuk; Kim, Hanjoo, et alARTICLE213 Coupling of FRAPCON for fuel performance analysis in the Monte Carlo code MCS
2020-05Coupled Neutronics-Thermal-Hydraulic Simulation of BEAVRS Cycle 1 Depletion by the MCS/CTF Code SystemYu, Jiankai; Lee, Hyunsuk; Kim, Hanjoo, et alARTICLE123 Coupled Neutronics-Thermal-Hydraulic Simulation of BEAVRS Cycle 1 Depletion by the MCS/CTF Code System
2020-05Validation of UNIST Monte Carlo Code MCS using VERA Progression ProblemsNguyen, Tung Dong Cao; Lee, Hyunsuk; Choi, Sooyoung, et alARTICLE179 Validation of UNIST Monte Carlo Code MCS using VERA Progression Problems
2020-05MCS/TH1D analysis of VERA whole-core multi-cycle depletion problemsNguyen, Tung Dong Cao.; Lee, Hyunsuk; Choi, Sooyoung, et alARTICLE134 MCS/TH1D analysis of VERA whole-core multi-cycle depletion problems
2020-05MCS – A Monte Carlo particle transport code for large-scale power reactor analysisLee, Hyunsuk; Kim, Wonkyeong; Zhang, Peng, et alARTICLE150 MCS – A Monte Carlo particle transport code for large-scale power reactor analysis
2020-04Fuel performance analysis of BEAVRS benchmark Cycle 1 depletion with MCS/FRAPCON coupled systemYu, Jiankai; Lee, Hyunsuk; Lemaire, Matthieu, et alARTICLE187 Fuel performance analysis of BEAVRS benchmark Cycle 1 depletion with MCS/FRAPCON coupled system
2020-04Simulations of BEAVRS Benchmark Cycle 2 Depletion with MCS/CTF Coupling SystemYu, Jiankai; Lee, Hyunsuk; Kim, Hanjoo, et alARTICLE161 Simulations of BEAVRS Benchmark Cycle 2 Depletion with MCS/CTF Coupling System
2020-04Conceptual design of long-cycle boron-free small modular pressurized water reactor with control rod operationJang, Jaerim; Choe, Jiwon; Choi, Sooyoung, et alARTICLE52 Conceptual design of long-cycle boron-free small modular pressurized water reactor with control rod operation
2020-02Neutronic simulation of China Experimental Fast Reactor start-up tests. Part I: SARAX code deterministic calculationDu, Xianan; Choe, Jiwon; Tran, Tuan Quoc, et alARTICLE207 Neutronic simulation of China Experimental Fast Reactor start-up tests. Part I: SARAX code deterministic calculation
2020-02Determination of the activity inventory and associated uncertainty quantification for the CROCUS zero power research reactorKim, Wonkyeong; Hursin, Mathieu; Pautz, Andreas, et alARTICLE209 Determination of the activity inventory and associated uncertainty quantification for the CROCUS zero power research reactor
2020-01Wire-Shaped 3D-Hybrid Supercapacitors as Substitutes for BatteriesKang, Kyeong-Nam; Ramadoss, Ananthakumar; Min, Jin-Wook, et alARTICLE252 Wire-Shaped 3D-Hybrid Supercapacitors as Substitutes for Batteries
2019-12Application of TULIP/STREAM code in 2-D fast reactor core high-fidelity neutronic analysisDu, Xianan; Choe, Jiwon; Choi, Sooyoung, et alARTICLE151 Application of TULIP/STREAM code in 2-D fast reactor core high-fidelity neutronic analysis
2019-11Verification of DeCART2D/CAPP code system for VHTR analysis with PMR-200 benchmarkJeong, Eun; Park, Jinsu; Lee, Hyun Chul, et alARTICLE202 Verification of DeCART2D/CAPP code system for VHTR analysis with PMR-200 benchmark
2019-09Uncertainty quantification of LWR-PROTEUS Phase II experiments using CASMO-5Park, Jinsu; Kim, Wonkyeong; Hursin, Mathieu, et alARTICLE192 Uncertainty quantification of LWR-PROTEUS Phase II experiments using CASMO-5
2019-08Development of integral type spent fuel pool storage rack with gadolinium and europium-containing structure materialsKim, Mi Jin; Kim, Wonkyeong; Lee, Deokjung, et alARTICLE271 Development of integral type spent fuel pool storage rack with gadolinium and europium-containing structure materials

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