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
Development of a Compact Real-Time Simulator for Two-Loop PWR Plant, FISA-2/PC No, Hee Cheon; Jeong, Jae Jun, Proc. of Third Intl. Topical Meeting on Nuclear Power Plant Thermal-Hydraulics and Operations , 1988 |
Three-Dimensional Two-Fluid Code for U-Tube Steam Generator Thermal Design Analysis No, Hee Cheon; Lee, Jae Young, Second Intl. Topical Meeting on Nuclear Power Plant Thermal-Hydraulics and Operations, 1986 |
Classification of Critical Heat Flux Patterns Based on Parametric Trends Using the Entropy Minimax Principle Baek, WP; Park, JW; Chang, Soon-Heung, International Conference on Multiphase Flow, pp.67 - 70, 1991 |
Conceptual Design of an Inherently Safe and Simple Tube Reactor Using Water as Moderator and Coolant Baek, WP; Chang, Soon-Heung, IAEA Tech. Committee Meeting on Progress in Devel. & Design Aspects of Water-Cooled Reactors, 1991 |
Development of an Expert System for Malfuction Diagnosis of Primary System in Nuclear Power Plant Chung, HY; Park, IS; Hur, SK; Cheon, SW; Kim, HG; Chang, Soon-Heung, The 3rd Symposium on Expert Systems Application to Power Systems, pp.539 - 547, 1991-04 |
Effect of Strain Aging on the Deformation Behavior in SA508-Cl.3 Nuclear Pressure Vessel 김인섭, Fall Meeting of Korean Nuclear Society, 1989 |
Derivation of Yield Stress in Beta-Transformed Zircaloy-4 Nuclear Fuel Sheaths 김인섭, Spring Meeting of Korean Nuclear Society, 1988 |
Effects of Texture and Microstructure on the Mechanical Properties of Heat-Treated Zircaloy-4 Kim, In Sup, Second International Conference on Candu Fuel, Chalk River, Canada, pp.1 - 5, 1989 |
A Study on the Microscopic Fracture Characteristics of A 533B-1 Nucler Pressure Vessel Steels Kim, In Sup, International Symposium on Pressure Vessel Technology, Seoul, Korea, pp.19 - 21, 1989 |
Effect of Microstructure on the Ductile Fracture of Ferrite-Martensite-Bainite Steels Kim, In Sup, Fall Meeting of TMS-AIME, Chicago, U.S.A., 1988 |
Changes of the Texture and Anisotropic Mechanical Properties in Zircaloy-4 Fuel Cladding due to the Effect of B-Heat Treatment Kim, In Sup, Fall Meeting of the Atomic Energy Society of Japan, 1987 |
Korean Experiences in Developing Nuclear Power Programme Byong-Whi Lee, Senior Expert Group Meeting, pp.1 - 3, 1986 |
Physical Modeling and Finite Element Method for the Analysis of Lateral Phase Distribution Phenomena Lee, GJ; Chang, Soon-Heung, International Conference on Multiphase Flow, Tsukuba, 1991 |
Prediction of Nuclear Reactor Parameters Using Artificial Neural Network Models Roh, MS; Cheon, SW; Kim, HG; Chang, Soon-Heung, The 2nd International Forum on the Expert Systems and Computer Simulation in Energy Eng., 1992-03 |
Mechanistic Flux Model of the Inverted Annular Film Boiling Ho, S.; Chang, Soon-Heung, The 9th International Heat Transfer Conference, pp.431 - 436, 1990 |
A Refined Mechanistic Critical Heat Flux Model for Upflow Boiling at Low Qualities Lee, KW; Chang, Soon-Heung, The 9th International Heat Transfer Conference, Jerusalem, pp.141 - 146, 1990 |
Time Dependent Analysis of Quenching Phemonenon with the Nonuniformity of Water Penetration Pattern in Hot Debris Bed Lee, KW; Chang, Soon-Heung, The 2nd International Topical Meeting on Nucl. Power Plant Ther. Hydrau. and Operation, pp.26 - 33, 1986-04 |
A Phenomenological Modeling for the High Pressure Melt Ejection from a Reactor Cavity 전문헌, 한국원자력학회 '90 춘계학술발표회 논문집 (I), pp.609 - 619, 1990 |
Analysis of Melting at the Wall in Laminar Flowin a Cylindrical Channel 전문헌, 한국원자력학회 '93 춘계학술발표회 논문집 (I), pp.383 - 394, 1990 |
A Large Dry PWR Containment Response Analysis for Postulated Severe Accidents 전문헌, 한국원자력학회 '87 춘계학술발표회, pp.30 - 31, 1987 |
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