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
CRX-Hex : A Transport Theory Code Based on Characteristic Method for Hexagonal Geometry Cho, Nam-Zin; Hong, S.G, Proc. of the Korean Nuclear Society Spring Meeting, pp.28 - 33, 1996-05 |
Design Charateristics of Moderation- Enhanced Reactor Core Loaded 100% with MOX Fuel Kim, Y.B; Cho, Nam-Zin, KAIF/KNS Annual Conference, 1996-03 |
CRX : A Characteristic Transport Theory Code for Cell and Assembly Calculations in Reactor Core Design Cho, Nam-Zin; Hong, S.G., Proc. of the Korean Nuclear Society Autumn Meeting, pp.85 - 90, 1995-10 |
A Multigroup Diffusion Nodal Scheme : Hybrid of AFEN and PEN Methods Cho, Nam-Zin; Noh, J.M., Proc. of the Korean Nuclear Society Autumn Meeting, pp.29 - 34, 1995-10 |
Development of a Three-Dimensional Nodal Diffusion Code Based on the AFEN Methodology Hong, S.G; Cho, Nam-Zin; Noh, J.M., Proc. of the Korean Nuclear Society Spring Meeting, pp.77 - 82, 1995-05 |
On the AFEN Method for Triangular Nodes in Hexagonal Assembly Cores Cho, Nam-Zin; Kim, D.S., Proc. of the Korean Nuclear Society Spring Meeting, pp.25 - 30, 1995-05 |
The Nodal Methods in Reactor Core Nuclear Design Cho, Nam-Zin, Proc. of the Korean Nuclear Society Spring Meeting, pp.45 - 53, 1995-05 |
Characteristics of Dynamic Strain Anging(DSA) in SA106GR.C Piping Steel 김인섭, Proc. of the Korean Nuclear Society Autumn Meeting, pp.771 - 776, 1995 |
열처리가 Zr-2.5Nb 압력관재료의 지체균열전파에 미치는 영향 김인섭, Proc. of the Korean Nuclear Society Autumn Meeting, pp.765 - 770, 1995 |
Compact Test Generation Of Robustly Hazard-Free Tests For Path Delay Fault In Combinational Circuits Using 19-Valued Logic Kim, Dae Sik; Seong, Poong-Hyun, Maintenance And Reliability Conference, pp.24 - 24, 1997-05 |
Development of a Charge Collection Model in CdZnTe Detectors and its Application to Gamma Spectrum Cho, Gyuseong; Kim, YS; Joo, KS, International Synposium on Solid State Detectors for the 21st Century, 1998 |
Analysis of the Void Wave Propagations : Wave Number Independent Characteristicse No, Hee Cheon; Song, Chul Hwa; Chung, Moon Ki, Proc. of the 7th Int'l Met. on Nuclear Reactor Thermal-Hydraulics(NURETH-7), 1995 |
The Effect of Bubble Flow Structures on the void Wave Propagations in a Large Diameter Pope No, Hee Cheon; Song, CH; Chung, MK, Proceedings of the International Confefence on Multiphase Flow, 1995 |
Comprehensive Promotion Plan for Utilization Research and Development of Nuclear Energy in Korea. Lee, Kun Jai, Proceedings of the Int'l Symp. "Energy Future in the Asia/Pacific Region"., pp.31 - 42, 1998 |
Evaluation of Thermal Embrittlement of Duplex Stainless Steel Using Small Punch Test Method 김인섭, 2nd Seminar on Nuclear Materials and Technology, KAERI, 1996 |
SA106Gr.C 주증기 배관재의 피로균열성장에 미치는 후열처리의 영향 김인섭, 국내원전기기의 건전성평가기술 워크샵, 1996 |
자기적 성질변화를 이용한 원자로 압력용기강의 조사효과평가 김인섭, Proc. of the Korean Nuclear Society Spring Meeting, pp.317 - 322, 1996 |
Accoustic Emission Behavior During Stress Corrosion Crcking of Inconel 600 김인섭, Proc. of the Korean Nuclear Society Spring Meeting, pp.145 - 150, 1996 |
Fatigue Crack Propagation Behavior in Butt Weldment of SA106Gr.C Main Steam Pipe Steel 김인섭, Proc. of the Korean Nuclear Society Spring Meeting, pp.92 - 97, 1996 |
Small Punch Test for the Evaluation of Thermal Aging Embrittlement of CF8 Duplex Stainless Steel 김인섭, Proc. of the Korean Nuclear Society Autumn Meeting, pp.79 - 84, 1996 |
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