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
Quantifying relative importance of NPP cyber attack probability variables based on factor analysis and AHP Kim, Yong Sik; Ryu, Ho Sun; Kim, Hyun Ki; Choi, Moon Kyoung; Lee, Chanyoung; Seong, Poong-Hyun, 11th Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies, NPIC and HMIT 2019, pp.1078 - 1087, American Nuclear Society, 2019-02 |
An overview of P-CMFD acceleration and its applications to reactor physics transport calculation Cho, Nam-Zin, 2017 Transactions of the American Nuclear Society, ANS 2017, pp.1247 - 1250, American Nuclear Society, 2017-10 |
Neutronic optimization of the reflector for a soluble-boron-free small modular reactor atom Nguyen, Xuan Ha; Yu, Hwanyeal; Kim, Yonghee, 2018 Transactions of the American Nuclear Society, ANS 2018, pp.1167 - 1170, American Nuclear Society, 2018-11 |
Thermodynamic approach to the chemical degradation of fly ash-blended concrete: Case study for Korean LILW trench type repository Han, Sol-Chan; Yun, Jong-Il, 2019 Transactions of the American Nuclear Society, ANS 2019, pp.159 - 161, American Nuclear Society, 2019-06 |
Feasibility of a very-low-boron core design for APR1400 with 24-month cycle length Do, Manseok; Nguyen, Xuan Ha; Kim, Yonghee, 2018 International Conference on Physics of Reactors: Reactor Physics Paving the Way Towards More Efficient Systems, PHYSOR 2018, pp.4048 - 4057, Sociedad Nuclear Mexicana, A.C., 2018-04 |
Analysis of the ACRR-ST-1 Experiment with the Integrated Severe Accident Analysis Code CINEMA 정운호; 정용훈, 2023 한국원자력학회 춘계학술발표회, 한국원자력학회, 2023-05-18 |
Thermal Performance Evaluation of Spent Fuel Pool Cooling System with Water Jacket and Heat Pipe 이상훈; 이민석; 박우성; 정용훈, 2023 한국원자력학회 춘계학술발표회, 한국원자력학회, 2023-05-18 |
Preliminary Evaluation of Thermal Performance for Spent Fuel Pool Passive Cooling System with Thermosyphon and Water Jacket Lee, Min Suk; Lee, Sanghoon; Park, Wooseong; Jeong, Yong Hoon, 2023 Ans Annual Meeting, American Nuclear Society, 2023-06-13 |
Improved modelling for the assembly discontinuity factors in the APEC method Kim, Woosong; Kim, Yonghee, 2017 Transactions of the American Nuclear Society, ANS 2017, pp.1093 - 1095, American Nuclear Society, 2017-06 |
Safety analyses of Kaist Micro modular reactor with modified Gamma+ code Oh, Bong-seong; Lee, Jeong-Ik; Kim, Seong Gu; Yu, Hwanyeal; Moon, Jangsik; Kim, Yonghee; Jeong, Yong Hoon, 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2017, Association for Computing Machinery, Inc, 2017-09 |
Efficiency investigation on electro-kinetic decontamination for concrete waste originated from nuclear power plants Kim, Chanyoung; Choi, Sungyeol; Kim, Seungpil; Shin, Myoungsu, 12th fib International PhD Symposium in Civil Engineering, 2018, pp.1227 - 1234, fib. The International Federation for Structural Concrete, 2018-08 |
A dryout model of crud Yeo, Dongyeol; No, Hee-Cheon, 2018 Transactions of the American Nuclear Society, ANS 2018 and Embedded Topical Meeting Nuclear Fuels and Structural Materials, pp.1281 - 1282, American Nuclear Society, 2018-06 |
A model for growth and fracture of crust before water ingression Yeo, Dongyeol; No, Hee-Cheon, 2018 Iron and Steel Technology Conference and Exposition, pp.1265 - 1267, Association for Iron and Steel Technology, AISTECH, 2018-05 |
Temperature feedback effect incorporated in hire-theoretic multigroup transport equations Jo, Yugwon; Cho, Nam-Zin, 2018 Transactions of the American Nuclear Society, ANS 2018 and Embedded Topical Meeting Nuclear Fuels and Structural Materials, pp.913 - 916, American Nuclear Society, 2018-06 |
Convergence of sequential and parallel one-node CMFD accelerations for neutron transport analysis Kim, Hyeon Tae; Kim, Yonghee, 2018 Transactions of the American Nuclear Society, ANS 2018 and Embedded Topical Meeting Nuclear Fuels and Structural Materials, pp.361 - 364, American Nuclear Society, 2018-06 |
Observation-based CHF model development: Dry spot - Dry patch models No, Hee-Cheon; Ha, Sang-Jun; Chu, In-Cheol; Choi, Jin Young, 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2017, Association for Computing Machinery, Inc, 2017-09 |
CFD-assisted analytical work of pressure vessel rupture size enlargement during severe accidents Song, Mun Won; No, Hee-Cheon, 2018 Iron and Steel Technology Conference and Exposition, pp.1263 - 1264, Association for Iron and Steel Technology, AISTECH, 2018-05 |
Application of the APEC method to MOx fuel loaded PWR cores Kim, Woosong; Kim, Yonghee, 2018 Transactions of the American Nuclear Society, ANS 2018 and Embedded Topical Meeting Nuclear Fuels and Structural Materials, pp.933 - 936, American Nuclear Society, 2018-06 |
Neutronics and Transient Analyses of a Supercritical CO2-cooled Micro Modular Reactor (MMR) Yu, HwanYeal; Hartanto, Donny; Oh, Bong-seong; Lee, Jeong-Ik; Kim, Yonghee, 5th International Symposium on Innovative Nuclear Energy Systems, INES-5 2016, pp.21 - 28, Elsevier Ltd, 2016-11 |
A diffusion-based 3D FEM analysis for assessment of reactivity change due to support plate expansion and localized flowering in an SFR Heo, Woong; Kim, Yonghee, 2018 Transactions of the American Nuclear Society, ANS 2018, pp.1245 - 1248, American Nuclear Society, 2018-11 |
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