Browse "NE-Journal Papers(저널논문)" by Title
Showing results 881 to 900 of 2827
| 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 |
| Development of a two-dimensional coupled-implicit numerical tool for analysis of the CDI operation Jeon, Byong Guk; No, Hee Cheon, DESALINATION, v.288, pp.66 - 71, 2012-03 |
| Development of a two-dimensional coupled-implicit numerical tool for the optimal design of CDI electrodes Jeon, Byong Guk; No, Hee Cheon; Lee, JeongIk, DESALINATION, v.274, no.1-3, pp.226 - 236, 2011-07 |
| Development of accelerated PCHE off-design performance model for optimizing power system operation strategies in S-CO2 Brayton cycle Kwon, Jin Su; Bae, Seong Jun; Heo, Jin Young; Lee, Jeong Ik, APPLIED THERMAL ENGINEERING, v.159, 2019-08 |
| Development of alumina-forming duplex stainless steels as accident-tolerant fuel cladding materials for light water reactors Kim, Hyunmyung; Jang, Hun; Subramanian, Gokul Obulan; Kim, Chaewon; Jang, Changheui, JOURNAL OF NUCLEAR MATERIALS, v.507, pp.1 - 14, 2018-08 |
| Development of an advanced human-machine interface for next generation nuclear power plants Chang, Soon-Heung; Choi, SS; Park, JK; Heo, GY; Kim, HG, RELIABILITY ENGINEERING SYSTEM SAFETY, v.64, no.1, pp.109 - 126, 1999-04 |
| Development of an advanced printed circuit heat exchanger analysis code for realistic flow path configurations near header regions Son, Seongmin; Lee, Youho; Lee, Jeong Ik, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.89, pp.242 - 250, 2015-10 |
| Development of an aluminide coating layer on Alloy 617 by Al sputtering and inter-diffusion heat treatments Kim, Dong-Hoon; Sah, Injin; Lee, Ho Jung; Hong, Sunghoon; Jang, Changheui, SURFACE & COATINGS TECHNOLOGY, v.244, pp.15 - 22, 2014-04 |
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