Browse "Dept. of Nuclear and Quantum Engineering(원자력및양자공학과)" by Type Article
Showing results 861 to 880 of 2779
| Development of a qualitative evaluation framework for performance shaping factors (PSFs) in advanced MCR HRA Lee, Seung-Woo; Kim, Ar-Ryum; Ha, Jun-Su; Seong, Poong-Hyun, ANNALS OF NUCLEAR ENERGY, v.38, no.8, pp.1751 - 1759, 2011-08 |
| Development of a quantitative evaluation method for non-technical skills preparedness of operation teams in nuclear power plants to deal with emergency conditions Yim, Ho Bin; Kim, Ar Ryum; Seong, Poong-Hyun, NUCLEAR ENGINEERING AND DESIGN, v.255, pp.212 - 225, 2013-02 |
| Development of a quantitative method for evaluating the efficacy of cyber security controls in NPPs based on intrusion tolerant concept Lee, Chanyoung; Yim, Ho Bin; Seong, Poong Hyun, ANNALS OF NUCLEAR ENERGY, v.112, pp.646 - 654, 2018-02 |
| Development of a quantitative resilience model for nuclear power plants Kim, Ji Tae; Park, Jooyoung; Kim, Jonghyun; Seong, Poong Hyun, ANNALS OF NUCLEAR ENERGY, v.122, pp.175 - 184, 2018-12 |
| Development of a real-time mobile gamma-ray measurement system for shipboard use Kim, Chang-Jong; Jang, Mee; Kim, Hyuncheol; Lim, Jong-Myoung; Lee, Wanno; Cho, Gyuseong, NUCLEAR ENGINEERING AND TECHNOLOGY, v.55, no.11, pp.4077 - 4082, 2023-11 |
| Development of a Real-Time Thermal Performance Diagnostic Monitoring System Using Self-Organizing Neural Network for KORI-2 Nuclear Power Unit Kang, Hyun-Gook; Seong, Poong-Hyun, NUCLEAR ENGINEERING AND TECHNOLOGY , v.28, no.1, pp.36 - 43, 1996-09 |
| Development of A Real-Time Thermal Performance Diagnostic Monitoring System Using Self-Organizing Neural Network for KORI-2 Nuclear Power Unit Kang, H.G.; Seong, P.H., 원자력학회지, v.28, no.1, pp.36 - 43, 1996-02 |
| Development of a remote monitoring and control system for nuclear power plants Lee, Seung Jun; Kim, M.S.; Kim, JongHyung; Seong, Poong-Hyun, TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, v.88, no.1, pp.70 - 70, 2003 |
| Development of a rule-based diagnostic platform on an object-oriented expert system shell Wang, Wenlin; Yang, Ming; Seong, Poong Hyun, ANNALS OF NUCLEAR ENERGY, v.88, pp.252 - 264, 2016-02 |
| Development of a Safety Analysis Method for Requirements Based on Statechart Using Combined SCR and ISO Tables Lee, Jung Hwan; Seong, Poong-Hyun, TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, v.85, pp.398 - 399, 2001-11 |
| Development of a safety critical software requirements verification method with combined CPN and PVS: a nuclear power plant protection system application Son, HS; Seong, Poong-Hyun, RELIABILITY ENGINEERING & SYSTEM SAFETY, v.80, no.1, pp.19 - 32, 2003-04 |
| Development of a scintillator-based optical soft x-ray (OSXR) diagnostic system for KSTAR tokamak Lee, M. W.; Kim, Junghee; Kim, M. H.; Lim, Soobin; Kim, Jayhyun; Sung, Choongki, REVIEW OF SCIENTIFIC INSTRUMENTS, v.94, no.5, 2023-05 |
| Development of a semi -empirical model -based COrium COolability analysis tool (COCOA) validated against a large scale corium experiment, FARO Kim, Jaeha; Yoon, S. H.; Song, Mun Won; No, Hee-Cheon, NUCLEAR ENGINEERING AND DESIGN, v.364, 2020-08 |
| Development of a semi-empirical model for forced convection film boiling on a sphere in water based on visual observations Yoon, Seung Hyun; No, Hee Cheon; Kim, Minju, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.127, pp.1180 - 1187, 2018-12 |
| Development of a short-term failure assessment of high density polyethylene pipe welds - Application of the limit load analysis Ryu, Ho-Wan; Han, Jae-Jun; Kim, Yun-Jae; Kim, Jong-Sung; Kim, Jeong-Hyeon; Jang, Changheui, TRANSACTIONS OF THE KOREAN SOCIETY OF MECHANICAL ENGINEERS, A, v.39, no.4, pp.405 - 413, 2015-04 |
| Development of a soft x-ray (SXR) array diagnostic system on versatile experiment spherical torus (VEST) Jang, Jae Young; Lim, Soobin; Kim, Seongcheol; Lee, MW; Kim, Young-Gi; Sung, Choongki; Hwang, YS, REVIEW OF SCIENTIFIC INSTRUMENTS, v.93, no.9, 2022-09 |
| Development of a thermal hydraulic analysis code for gas-cooled reactors with annular fuels Han, KH; Seo, KW; Hwang, DH; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.236, no.2, pp.164 - 178, 2006-01 |
| Development of a thermal-hydraulic analysis code for annular fuel assemblies Han, KH; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.226, no.3, pp.267 - 275, 2003-12 |
| Development of a tokamak reactor system code and its application for concept development of a demo reactor Hong, Bong Guen; Lee, Dong Won; Kim, Suk-Kwon; Kim, Yonghee, FUSION ENGINEERING AND DESIGN, v.83, no.10-12, pp.1615 - 1618, 2008-12 |
| Development of a Traceability Analysis Method Based on Case Grammar for NPP Requirement Documents Written in Korean Language 유영제; 김만철; 성풍현, NUCLEAR ENGINEERING AND TECHNOLOGY , v.36, no.4, pp.295 - 303, 2004-08 |
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