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D

Deokjung Lee

ulsan national institute of science and technology

24H指数
272论文数
2.1K被引数
收录论文 43
发表时间
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Neutronic and depletion analysis of a 5 MWth heat pipe cooled reactor with TRISO fuel and fluoride salt using MCS采用MCS方法对采用TRISO燃料和氟盐、由热管冷却的5 MWth反应堆进行中子学和燃耗分析
errNuclear Engineering and Technology
IF2.6
err2026-08-01
err0
PREAI
errKim, Kyeongwon; Jeong, Hae-Yong; Lee, Deokjung
err分享
err收藏
Neutronic Performance and Safety Analysis of FeCrAl-Coated SiC Reflector in a Boron-Free SMR using LEU+ Fuel在无硼小型模块化反应堆中使用LEU燃料时FeCrAl涂层SiC反射层的中子性能与安全分析
errNuclear Engineering and Technology
IF2.6
err2026-05-19
err0
errOAAI
errYeongseok Kang; Jinsu Park; Yongsik Yang; Changhwan Shin; Deokjung Lee
err分享
err收藏
Explicit and simplified modeling of in-core instrument for emitter region reaction rate calculation using STREAM/RAST-K利用STREAM/RAST-K对堆芯仪表进行显式和简化的建模，以计算发射区反应率
errNuclear Engineering and Technology
IF2.6
err2026-03-03
err0
errOAAI
errKyeongwon Kim; Dongmin Yun; Wonkyeong Kim; Sung Ju Kwon; Setiawan Fathurrahman; Deokjung Lee
err分享
err收藏
Editorial: Multiphysics methods and analysis applied to nuclear reactor systems (vol 4 , 1717262 , 2025)编辑：多物理场方法及其在核反应堆系统中的应用分析（卷 4，1717262，2025）
errFrontiers in Nuclear Engineering
IF0
err2025-12-17
err1
errOAAI
errDeHart, Mark D.; Shemon, Emily; Lee, Deokjung
err分享
err收藏
Enhanced Fidelity of Monte Carlo Coupled Multi-Physics Simulations in the MCS codeMCS代码中耦合多物理场模拟的增强保真度
errNuclear Engineering and Technology
IF2.6
err2025-12-10
err0
errOAAI
errMuhammad Imron; Deokjung Lee
err分享
err收藏
Enhancing CMFD Acceleration in MOC-based Direct Transport Code增强基于MOC的直接输运代码中的CMFD加速
errNuclear Engineering and Technology
IF2.6
err2025-12-09
err0
errOAAI
errFathurrahman Setiawan; Siarhei Dzianisau; Deokjung Lee
err分享
err收藏
Axially decomposed GPU-enabled three-dimensional method of characteristics/diamond difference solver in neutron transport code STREAM3D-GPU轴向分解的GPU加速三维特征线法/钻石差分求解器在中子输运代码STREAM3D-GPU中
errComputer Physics Communications
IF3.4
err2025-11-12
err0
PREAI
errSiarhei Dzianisau; Deokjung Lee
err分享
err收藏
Development of New GPU-Optimized Reactor Physics Monte Carlo Code GREAPMC新型GPU优化反应堆物理蒙特卡洛程序GREAPMC的开发
errNUCLEAR SCIENCE AND ENGINEERING
IF1.3
err2025-11-01
err0
PREAI
errAli, Muhammad Rizwan; Aygul, Murat Serdar; Lee, Deokjung
err分享
err收藏
Editorial: Multiphysics methods and analysis applied to nuclear reactor systems
errFrontiers in Nuclear Engineering
IF0
err2025-10-24
err0
errOAAI
errDeHart, Mark D.; Shemon, Emily; Lee, Deokjung
err分享
err收藏
GREAPMC: development status, capabilities, and future developmentsGREAPMC：发展现状、能力及未来发展方向
errEPJ NUCLEAR SCIENCES & TECHNOLOGIES
IF0
err2025-09-16
err0
errOAAI
errAli, Muhammad Rizwan; Aygul, Murat Serdar; Lee, Deokjung
err分享
err收藏
Development of cross-section model of two-step code system considering control rod depletion for soluble boron free operation of SMR考虑控制棒消耗的两步法代码系统截面模型的开发，以实现SMR的无溶硼运行
errProgress in Nuclear Energy
IF3.2
err2025-07-26
err0
PREAI
errJinsu Park; Wonkyeong Kim; Yeongseok Kang; Wisoo Jeong; Changhyun Lim; Jooil Yoon; Deokjung Lee
err分享
err收藏
Uncertainty quantification of steady state depeltion solution using multi-physics coupling code system based on nodal diffusion code RAST-K基于节点扩散程序RAST-K的多物理场耦合代码系统对稳态耗尽解的不确定性量化
errNuclear Engineering and Technology
IF2.6
err2025-06-13
err0
errOAAI
errJinsu Park; Yeongseok Kang; Deokjung Lee
err分享
err收藏
Application of artificial neural network for assembly homogenized equivalence parameter generation
errPROGRESS IN NUCLEAR ENERGY
IF3.2
err2024-08-01
err0
PREAI
errDzianisau, Siarhei; Lee, Deokjung
err分享
err收藏
Group constants generation by Monte Carlo code MCS for LWR analysis
errCOMPUTER PHYSICS COMMUNICATIONS
IF3.4
err2023-04-01
err1
PREAI
errNguyen, Tung Dong Cao; Lee, Deokjung
err分享
err收藏
A novel SN/MOC collaborative method for few-group cross-section generation with versatile neutron spectral adaptability in advanced reactor physics analysis
errCOMPUTER PHYSICS COMMUNICATIONS
IF3.4
err2022-07-01
err1
PREAI
errWei, Linfang; Lee, Deokjung; Lee, Hyun Chul
err分享
err收藏
Development of high-fidelity neutron transport code STREAM?
errCOMPUTER PHYSICS COMMUNICATIONS
IF3.4
err2021-07-01
err24
PREAI
errChoi, Sooyoung; Kim, Wonkyeong; Choe, Jiwon; Lee, Woonghee; Kim, Hanjoo; Ebiwonjumi, Bamidele; Jeong, Eun; Kim, Kyeongwon; Yun, Dongmin; Lee, Hyunsuk; Lee, Deokjung
err分享
err收藏
MicroURANUS: Core design for long-cycle lead-bismuth-cooled fast reactor for marine applicationsMicroURANUS: 用于海洋应用的长周期铅铋冷却快堆的核心设计
errINTERNATIONAL JOURNAL OF ENERGY RESEARCH
IF4.2
err2021-03-24
err19
errOAAI
errNguyen, Tung Dong Cao; Khandaq, Muhammad Farid; Jeong, Eun; Choe, Jiwon; Lee, Deokjung; Fynan, Douglas A.
err分享
err收藏
Three-dimensional method of characteristics/diamond-difference transport analysis method in STREAM for whole-core neutron transport calculation?
errCOMPUTER PHYSICS COMMUNICATIONS
IF3.4
err2021-03-01
err27
PREAI
errChoi, Sooyoung; Lee, Deokjung
err分享
err收藏
A PCA compression method for reactor core transient multiphysics simulation
errPROGRESS IN NUCLEAR ENERGY
IF3.2
err2020-10-01
err8
PREAI
errCherezov, Alexey; Jang, Jaerim; Lee, Deokjung
err分享
err收藏
Coupling of FRAPCON for fuel performance analysis in the Monte Carlo code MCS
errCOMPUTER PHYSICS COMMUNICATIONS
IF3.4
err2020-06-01
err3
PREAI
errYu, Jiankai; Lee, Hyunsuk; Kim, Hanjoo; Zhang, Peng; Lee, Deokjung
err分享
err收藏

研究方向

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合作学者
合作期刊
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Seok Ju Kang
H 指数: 47 · 论文数: 197
H
Ho Cheol Shin
H 指数: 46 · 论文数: 262
A
Ananthakumar Ramadoss
H 指数: 46 · 论文数: 169
K
Kord Smith
H 指数: 28 · 论文数: 173
H
Hyunsuk Lee
H 指数: 24 · 论文数: 188
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