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전체 가 나 다 라 마 바 사 아 자 차 카 타 파 하

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Showing results 201 to 220 of 1,244

Issue Date	Title / Author(s) / Citation	File
2016-08	Development of a System Dynamics Model for the Assessment of Nuclear Security Culture at a Nuclear Power Plant 이건희	view file
2012-08	Development of a Transient Gas-Liquid Pipe Flow Using Drift-Flux Approach 최진호	view file
2019-06	Development of a two-regime heat conduction model for TRISO-based nuclear fuels Liu, Maolong; Thurgood, Jared; Lee, Youho; Rao, Dasari, V Journal of Nuclear Materials, Vol.519, pp.255-264	DOI
1996	Development of a uncertainty quantification method for large break loss of coolant accident in pressurized water reactor 이영진	link
2014-02	Development of a Vector Following Mesh Generator for Analysis of Two Dimensional Tokamak Plasma Transport 김영진	view file
2018-08	Development of Advanced Leakage Feedback Method for Two-step Core Analyses 반영석	view file
2022	Development of Advanced Time-dependent Monte Carlo Neutron Transport Methods for Reactor Transient Analysis 장상훈	view file link
2002	Development of an analytical model for local hydrogen behavior analysis in NPP containment 최용석	link
2016-08	Development of an assessment technique for subsidence risk in mining areas using strength reduction method 전병규	view file
2022-10	Development of an energy and efficiency calibration method for stilbene scintillators Kim, Chanho; Kim, Jaehyo; Hong, Wooseong; Yeom, Jung-Yeol; Kim, Geehyun Nuclear Engineering and Technology, Vol.54 No.10, pp.3833-3840	DOI
2006	Development of an integral test loop, HELIOS and investigation of natural circulation ability for PEACER 정승호	link
2005	Development of an integrated design model for PEACER fuel rod design and creep analysis 남원창	link
2022-08	Development of an operation trajectory design algorithm for control of multiple 0D parameters using deep reinforcement learning in KSTAR Seo, J.; Na, Yong Su; Kim, B.; Lee, C. Y.; Park, M. S.; Park, S. J.; Lee, Y. H. Nuclear Fusion, Vol.62 No.8, p. 086049	DOI
2017-08	Development of Anode Spot Plasma Ion Source for High Current Beam Extraction 이윤아	view file
1997	Development of ceramic humidity sensor for the Korean next generation reactor 이나영	link
2008	Development of CFD code for subcooled boiling two-phase flow with modeling the interfacial area transport equation 배병언	link
2023	Development of Dynamic LES-SPH Method for Thermal Ablation Analysis with Turbulent Natural Convection 최태수	view file link
2023	Development of Dynamic Simulation Model for 10 kWe Heat Pipe Micro Fission Battery using AMESIM 지종성	view file link
2017-02	Development of Effective Applied Moment Formulations for Integrity Assessment of Nuclear Piping Systems under Static and Dynamic Loading Conditions 김예지	view file
2001	Development of effervescence model and improvement of subcooled boiling heat transfer model for dissolved noncondensible gas in reactor coolant system 정익	link

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