NE-Conference Papers(학술회의논문)

Recent Items

Collection's Items (Sorted by Submit Date in Descending order): 161 to 180 of 5619

161
Preliminary analysis of hydrogen production of water electrolysis using NPP

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

162
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

163
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

164
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

165
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

166
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

167
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

168
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

169
Performance evaluation of higher-order numerical scheme for application of 1D nuclear system analysis code

Lee, Won Woong; Lee, Jeong-Ik, 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2017, Association for Computing Machinery, Inc, 2017-09

170
Ultra-small radiation hardened instrumentation for wireless radiation detection sensor network

Kwon, Inyong; Kim, Chang Hwoi; Cho, Gyuseong, 11th Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies, NPIC and HMIT 2019, pp.1795 - 1802, American Nuclear Society, 2019-02

171
FAST (Floating Absorber for Safety at Transient) for the improved safety of metallic-fuel-loaded sodium-cooled fast reactors

Kim, Chihyung; Kim, Yonghee, Transactions of the American Nuclear Society, ANS 2019, pp.1545 - 1548, American Nuclear Society, 2019-11

172
Recession of CVD silicon carbide in steam environment

Park, Byung Ha; No, Hee-Cheon, Transactions of the American Nuclear Society, ANS 2018, pp.959 - 961, American Nuclear Society, 2018-11

173
Feasibility of applying a human bio-ignals monitoring to minimize insider threats

Suh, Young A; Yim, Man-Sung, Transactions of the American Nuclear Society, ANS 2017, pp.307 - 309, American Nuclear Society, 2017-06

174
Study on the assessment method of human error probabilities in the digitalized main control room

Kim, Ar Ryum; Kim, Ji Tae; Chae, Young Ho; Seong, Poong-Hyun; Jang, Inseok, 10th International Topical Meeting on Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies, NPIC and HMIT 2017, pp.506 - 514, American Nuclear Society, 2017-06

175
Feasibility study of TES integrated PWR nuclear power plant

Lee, Ju Yeon; Lee, Jeong-Ik, 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019, pp.1452 - 1461, American Nuclear Society, 2019-08

176
Preliminary study of the conceptual design of the Atom Safety System

Seo, Gwang Hyoek; Shin, Doyoung; Son, Hong Hyun; Kim, Sung Joong; Kim, Yonghee; Lee, Jeong-Ik, 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2017, Association for Computing Machinery, Inc, 2017-09

177
The roles of transport partial current information in two-level p-CMFD acceleration in the whole-core transport calculation

Cho, Nam-Zin, Transactions of the American Nuclear Society, ANS 2019, pp.1323 - 1326, American Nuclear Society, 2019-11

178
Smooth manifold extraction for 2D synthetic radiography using 2D CNT array-based DTS system

Soh, Jeongtae; Hyun, Subong; Kim, Hyeongseok; Ito, Mikiko; Jung, Young-jun; Kim, Tae-Hyung; Cho, Seungryong, Medical Imaging 2023: Image Processing, SPIE, 2023-02-19

179
Effective phantom design for an accurate geometry calibration in an offset-detector-based cone-beam CT system

Hwang, Jaehong; Kim, Hyeongseok; Lee, Taewon; Choi, Da-in; Kwon, Taejin; Kim, Yejin; Cho, Seungryong, International Forum on Medical Imaging in Asia 2023, IFMIA, 2023-01-10

180
Penalty driven enhanced self-supervised learning (Noise2Void) for CBCT denoising

Yun, Sungho; Jeong, Uijin; Kwon, Taejin; Choi, Da-in; Lee, Taewon; Ye, Sung-Joon; Cho, Gyuseong; et al, Medical Imaging 2023: Physics of Medical Imaging, SPIE, 2023-02-22

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