Choi, Da-in; Yun, Sungho; Cho, Seungryong, AAPM 2024 (66th Annual Meeting & Exhibition), 2024-07-25
Hwang, Joonil; Park, Sangjoon; Cho, Seungryong; Kim, Jin Sung, AAPM 2024 (66th Annual Meeting & Exhibition), 2024-07-21
Donghyun, Kim; Lee, Seoyoung; Hyun, SuBong; Cho, Seungryong, AAPM 2024 (66th Annual Meeting & Exhibition), 2024-07-21
Hyun, Subong; Lee, Seoyoung; Jeong, Uijin; Cho, Seungryong, 17th International Workshop on Breast Imaging (IWBI 2024), 2024-06-11
Lee, Seoyoung; Hyun, Subong; Kim, Donghyun; Cho, Seungryong, 17th International Workshop on Breast Imaging (IWBI 2024), 2024-06-10
최다인; 윤성호; 조승룡, 제 67회 한국의학물리학회 춘계학술대회, 2024-04-13
황준일; 박상준; 조승룡; 김진성, 제 67회 한국의학물리학회 춘계학술대회, 2024-04-12
현수봉; 조승룡, 제 67회 한국의학물리학회 춘계학술대회, 2024-04-12
Yun, Sungho; Choi, Da-in; Cho, Gyuseong; Ye, Sung-Joon; Cho, Seungryong, Medical Imaging 2024: Physics of Medical Imaging, 2024-02-21
Kim, Gibok; Yun, Sungho; Lee, Taewon; Cho, Seungryong, Medical Imaging 2024: Physics of Medical Imaging, 2024-02-21
Decision Analysis for Nuclear Fuel Cycle Policy 이건재, 제 2 회 KAIF/KNS Joint Annual Conference, pp.28 - 30, 1987 |
열교환기 튜브 조건이 비등 열전달에 미치는 영향에 대한 실험적 연구 전문헌, Proc. of the Korean Nuclear Society Autumn Meeting, Seoul, Korea, pp.257 - 264, 1994 |
Assessment of Two Uncertainty Quantification Methods for Source Term Analysis 전문헌, Proc. of the Korean Nuclear Society Spring Meeting, Pohang, pp.497 - 502, 1994 |
열교환기 튜브 구조가 열전달과 탱크 내부 온도에 미치는 영향에 대한 실험적 연구 전문헌, Proc. of the Korean Nuclear Society Spring Meeting, Pohang, pp.379 - 384, 1994 |
Effects of Interfacial Shear Between the Gas and Turbulent Falling Liquid Film on Heat Transfer Coefficient 전문헌, Proc. of the Korean Nuclear Society Spring Meeting, Pohang, pp.317 - 323, 1994 |
A Semi-Empirical Correlation for an Adiabatic Interfacial Friction Factor 전문헌, Proc. of Korean Nuclear Society Autumn Meeting, Seoul, Korea, pp.29 - 34, 1993 |
An Experimental Study on the Flow Instabilities and Critical Heat Flux under Natural Circulation Kim, YI; Chang, Soon-Heung, The 4th Internation Topical Meeting on Nuclear Thermal Hydraulics, Operations and Safety, 1994-04 |
A Study on the Optimal Fuel Loading Pattern Design in Pressurized Water Reactor Using the Artificial Neural Network and Fuzzy Rule Based System Lee, BH; Kim, HG; Chang, Soon-Heung, The IAEA Tech. Committee Meeting on Progress in Devel. & Design Aspects of Water-Cooled Rea, 1994 |
Nonlinear Model-Based Robust Control of a Nuclear Reactor Using Adaptive PIF Gains and Variable Structure Controller Park, M.G; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Autumn Meeting, pp.285 - 290, 1992-10 |
Convergence Analysis of the Parallel Schwarz Algorithm with Under-Relaxation in Pseudo- Boundary Conditions Kim, Y.H; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Autumn Meeting, Seoul, pp.223 - 228, 1992-10 |
Generation of Gamma-Ray Streaming Kernels Through Cylindrical Ducts via Monte Carlo Method Kim, D.S; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Spring Meeting, pp.667 - 672, 1992-05 |
An Expansion Method for Determining Asymptotic Stability Domains of Nonlinear Reactors Yang, C.Y; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Spring Meeting, pp.447 - 452, 1992-05 |
Adomian Decomposition Method for the Reactor Point Kinetics Cho, Y.C; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Spring Meeting, pp.67 - 72, 1992-05 |
Generation of Spatial Weighting Functions for Ex-Core Detectors by Adjoint Transport Calculation Ahn, J.G; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Spring Meeting, pp.15 - 20, 1992-05 |
Development of Finite Element Method of Body Fit Nodalization for Mixed Convection Analysis in Rod Bunbles Lee, GJ; Chang, Soon-Heung, The 3rd Internation Topical Meeting on Nuclear Reactor Plant Thermal Hydraulics and Operation, 1988 |
Domain Decomposition Solution of the Neutron Diffusion Equation with an Iterative Parallel Algorithm on a Transputer Network Kim, Y.H; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Autumn Annual Meeting, pp.125 - 130, 1991-10 |
An Analytic Relations Method for the Calculation of Actinides Concentrations Chang, D.I; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Spring Annual Meeting, pp.499 - 504, 1991-05 |
A Compute Code for Common-Cause Failure Analysis Park, B.H; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Spring Annual Meeting, pp.341 - 346, 1991-05 |
Solution of Neutron Diffusion Equation on a Parallel Computer Kim, Y.H; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Spring Annual Meeting, pp.75 - 80, 1991-05 |
Variance Reduction Techniques for Uncertainty Analysis of Fault Trees Choi, J.S; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Spring Annual Meeting, 1990-05 |
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