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College of Engineering(공과대학)Dept. of Nuclear and Quantum Engineering(원자력및양자공학과)

NE-Conference Papers(학술회의논문)

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Collection's Items (Sorted by Submit Date in Descending order): 141 to 160 of 5611

141
Dual-domain network with transfer learning for reducing bowtie-filter induced artifacts in half-fan cone-beam CT

Yun, Sungho; Jeong, Uijin; Lee, Donghyeon; Kim, Hyeongseok; Cho, Seungryong, 7th International Conference on Image Formation in X-Ray Computed Tomography, SPIE, 2022-06

142
DETERMINATION OF IRRADIATED STAINLESS STEEL PROPERTIES AND ITS EFFECTS ON REACTOR VESSEL INTERNALS

Kwak, Dong-Hyeon; Sim, Jae Min; Chang, Yoon-Suk; Kong, Byeng Seo; Jang, Changheui, ASME 2022 Pressure Vessels and Piping Conference, PVP 2022, American Society of Mechanical Engineers (ASME), 2022-07

143
Transient Analysis of Hybrid Micro Modular Reactor Using GAMMA+ Code

Choi, Sungwook; Lee, Jeong-Ik, 8th Japan-Korea Joint Seminar on Nuclear Thermal Hydraulics and Safety for Students and Young Researchers, NTHAS12 Joint Seminar, 2022-10-29

144
Many-view under-sampling (MVUS) technique for low-dose CT: Dose versus image quality

Lee, Taewon; Min, Jonghwan; Cho, Seungryong, 2012 IEEE Nuclear Science Symposium and Medical Imaging Conference Record, NSS/MIC 2012, pp.3617 - 3619, The Nuclear and Plasma Sciences Society, Institute of Electrical and Electronic Engineers, 2012-10

145
Mechanical properties of ion-irradiated stainless steel determined by nanoindentation tests and finite element analyses

Sim, Jae Min; Chang, Yoon-Suk; Kong, ByeongSeo; Jang, Changheui, ASME 2020 Pressure Vessels and Piping Conference, PVP 2020, American Society of Mechanical Engineers (ASME), 2020-08-03

146
Numerical analysis of single-phase thermal hydraulic parameters along nanostructured coating film

Al-Yahia, Omar S; Addad, Yacine; Yoon, Ho Joon; Cho, Sung Oh, International Conference on Nuclear Engineering, ICONE 2020, collocated with the ASME 2020 Power Conference, American Society of Mechanical Engineers (ASME), 2020-08

147
Preliminary Analysis of Two-Phase Expansion on Liquid Air Energy Storage System Integrated to a Conventional Pressurized Water Reactor

Chae, YongJae; Patk, JungHwan; Kumar, Amit; Haglind, Fredrik; Lee, Jeong-Ik, International Congress on Adavances in Nuclear Power Plants (ICAPP 2023), Korea Nuclear Society (KNS), 2023-04-24

148
Thermodynamic analysis of a Conventional PWR Integrated with Compressed 〖CO〗_2 Energy Storage System

채용재; 박정환; 오승환; 정용주; 이정익, 2020 한국원자력학회 춘계 학술발표회, 한국원자력학회, 2020-07-09

149
Thermodynamic Study of Compressed CO₂ Energy Storage System Integrated to a Conventional PWR

채용재; 정용주; 이정익, 2020 한국원자력학회 추계 학술발표회, 한국원자력학회, 2020-12

150
Thermodynamic Study of Liquid CO₂ Energy Storage System Integrated to a Conventional PWR

채용재; 이정익, 2021 한국원자력학회 춘계 학술발표회, 한국원자력학회, 2021-05-13

151
Off-design Performance Analysis of Compressed CO₂ Energy Storage System Integrated to a Conventional PWR

채용재; 이정익, 2021 한국원자력학회 추계 학술발표회, 한국원자력학회, 2021-10-21

152
Economic Analysis of Liquid CO2 Energy Storage System Integrated to a Conventional PWR

채용재; 이정익, 2022 한국원자력학회 춘계 학술발표회, 한국원자력학회, 2022-05-19

153
Preliminary analysis of hydrogen production of water electrolysis using NPP

채용재; 이정익, 2022 한국원자력학회 추계 학술발표회, 한국원자력학회, 2022-10-20

154
Thermodynamic analysis of various electrolysis methods integrated to Small Modular Reactor for hydrogen production

채용재; 박정환; 이정익, 2023 한국원자력학회 춘계 학술발표회, 한국원자력학회, 2023-05-18

155
Advancements in the Development of Low Enriched Uranium Nuclear Thermal Rockets

Venneri, Paolo; Kim, Yonghee, 5th International Symposium on Innovative Nuclear Energy Systems, INES-5 2016, pp.53 - 60, Elsevier BV, 2016-10

156
Artificial neural network modeling for 2-group pin-wise group constants

Yu, HwanYeal; Ur Rehman, Haseeb; Kim, Yonghee, Transactions of the American Nuclear Society, ANS 2017, pp.1107 - 1110, American Nuclear Society, 2017-06

157
In-situ corrections of two-group assembly cross-sections and discontinuity factors by the APEC method

Kim, Woosong; Kim, Yonghee, Transactions of the American Nuclear Society, ANS 2017, pp.1440 - 1443, American Nuclear Society, 2017-10

158
Partial procedure based automation using by APR1400 computerized procedure system

Seong, Nokyu; Jung, Yeonsub; Sung, Chanho; Seong, Poong-Hyun, 11th Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies, NPIC and HMIT 2019, pp.1478 - 1484, American Nuclear Society, 2019-02

159
One-node CMFD formulations for multi-group SP3equations in hexagonal geometry

Jang, Seongdong; Kim, Yonghee, International Conference on Physics of Reactors: Reactor Physics Paving the Way Towards More Efficient Systems, PHYSOR 2018, pp.3178 - 3189, Sociedad Nuclear Mexicana, A.C., 2018-04

160
Suggestion of initiating threats and bounding groups for NPP cyber risk assessment

Han, Sang Min; Seong, Poong-Hyun, 11th Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies, NPIC and HMIT 2019, pp.1088 - 1094, American Nuclear Society, 2019-02

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