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
KIGEN - A Computer Code for Decay Heat Calculation by Analytic Relations Cho, Nam-Zin; Lee, Y.J, Proc. of the Korean Nuclear Society Spring Annual Meeting, 1990-05 |
An Observer-Theoretic Approach to Estimating Neutron Flux Distribution Park, Y.H; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Annual Meeting, 1989-10 |
An Improved Maximum Entropy Method for the Reconstruction Problem in Nodal Calculation Jung, W.S; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Annual Meeting, 1989-10 |
MARAS - A Computer Code for Semi-Markov Reliability Analysis of Alternating Systems Lee, K.N; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Annual Meeting, 1989-05 |
MARADD - A Computer Code for Semi-Markov Reliability Analysis of Test/Repair Policies for Standby Safety Systems Jung, W.S; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Annual Meetign, 1989-05 |
Maximum Entropy Method for the Reconstruction Problem in Nodal Calculation : Preliminary Results Na, W.J; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Annual Meeting, 1989-05 |
Optimal Control of Xenon Concentration via Observer Design Woo, H.S; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Annual Meeting, 1989-05 |
A Spectral Form Function Method for Reconstructing Pointwise Flux Distributions Jeong, H.Y; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Annual Meeting, 1988-05 |
SLIM/SVD - A Computer Code for Evaluation of System-Level Importance Measures in Probabilistic Safety Analysis of Nuclear Power Plants Jung, W.S; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Annual Meeting, 1988-05 |
On the Multiplicity of Power Distributions in a Nuclear Reactor under Reactivity Feedback Effects Yang, C.Y; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Annual Meeting, 1987-10 |
Determination of Intermediate-Level Performance Criteria for Improvement of Nuclear Power Plant Design and Operation Jung, W.S; Cho, Nam-Zin, International Topical Meeting on Probabilistic Safety Assessment, pp.1366 - 1372, 1993-01 |
Implementation of a Parallel Algorithm in 2-D Assembly Transport Calculation on a Transputer Cho, Nam-Zin; Song, J.S, Proc. of the International Symposium on Numerical Transprot Theory, Moscow, Russia, pp.72 - 75, 1992-05 |
A Lyapunov Function-Free Method for Stability Domains of Nonlinear Reactors Yang, C.Y; Cho, Nam-Zin, Proc. of the 1992 Topical Meeting on Advances in Reactor Physics, v.2, pp.433 - 444, 1992-03 |
Cell Homogenization Method for Strongly Heterogeneous Research Reactors Lee, J.T; Lee, B.H; Cho, Nam-Zin; Oh, S.K, Proc. of the International Topical Meeting on Advanced in Math. Computation, and Reactor Physics, v.3, pp.1 - 12, 1991-04 |
Reconstruction of Pointwise Neutron Flux Distribution via Minimum Cross-Entropy Principle Jung, W.S; Cho, Nam-Zin, Proc. of the International Topical Meeting on Advances in Mathmatics, Computation, and Reactor Physi, pp.1 - 12, 1991-04 |
A New Method for Reconstructing Pointwise Flux Distribution Based on Maximum Entropy Principle Jung, W.S; Cho, Nam-Zin, Proc. of the International Conference on the Physics of Reactors:Operation, Design and Computation, v.2, pp.1 - 10, 1990-04 |
Development of OASYS Using Rule- and Fuzzy-Based Expert System for Nuclear Power Plants Kang, KS; Choi, SS; Kim, HG; Chang, Soon-Heung, '94 ANS Winter Meeting, pp.119 - 121, 1994 |
Classification and Assessment of CHF Data in Round Tubes at Low Velocities Chang, Soon-Heung, The IAEA Tech. Committee Meeting on Progress in Devel. & Design Aspects of Water-Cooled Reactor, pp.341 - 349, 1994 |
A Mechanistic CHF Model for Liquid Metals Based on Flow Excursion Mechanism Lee, YB; Chang, Soon-Heung, The IAEA Tech. Committee Meeting on Progress in Devel. & Design Aspects of Water-Cooled Reactor, 1994 |
Characteristics of Radiocolloid 이건재, 한국원자력학회 학술발표회 ( 추계 ), pp.123 - 127, 1992 |
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