Browse "NE-Conference Papers(학술회의논문)" by Title
Showing results 281 to 300 of 5619
| A Quantitative Approach to the Information Processing Capacity of Main Control Room Operators in Nuclear Power Plant Kim, Ji Tae; Seong, Poong-Hyun, 대한인간공학회 2006 춘계학술대회, 대한인간공학회, 2006-05-25 |
| A Quantitative Assessment Method for the NPP Operators' Diagnosis of Accidents 김만철; 성풍현, 한국원자력학회 2003 춘계학술발표회, pp.96 - 96, 한국원자력학회, 2003-05 |
| A Quantitative Assessment Method for Trip Signal Generation Failures 신승기; 성풍현, 한국원자력학회 2010 춘계학술발표대회, 한국원자력학회, 2010-05-28 |
| A Quantitative Impact Analysis of Sensor Failures on Human Operator's Decision Making in NPP Seong, Poong-Hyun, NUTHOS-6, 2004-10 |
| A quantitative impact analysis of sensor failures on nuclear power plant operators in accident situations Kim, M.C.; Seong, Poong-Hyun, 2005 Annual Meeting - American Nuclear Society, v.92, pp.451 -, 2005-06-05 |
| A Quantitative Method for the Fault Coverage of Watchdog Timers in NPP Digital Systems 김만철; 김석준; 성풍현, 한국원자력학회 2003 춘계학술발표회, pp.90 - 90, 한국원자력학회, 2003-05 |
| A Quantitative Model of System Man Interaction based on Discrete Function Theory Kim, Man Cheol; Seong, Poong-Hyun, International Seminar on Human-Centered Automation and Software Reliability of Man-Machine Systems from Cognitive Engineering Aspect, pp.101 - 125, 2001-07 |
| A Quantitative Model of System Man Interaction Using Discrete Functions 김만철; 성풍현, 한국원자력학회 2001 추계학술발표회, pp.86 - 86, 한국원자력학회, 2001-10 |
| A Quick Review on Steam Generator Water Level Tracking Methods and Its Uncertainties Park, Ki Moon; Lee, Jeong-Ik, The Korean Nuclear Society Spring Meeting(2016), The Korean Nuclear Society, 2016-05-12 |
| A Rapidly Convergent Generalized Rebalance Method (GRM) for Discrete Ordinates Transport Equations Hong, S.G; Cho, Nam-Zin; Kim, K.S; Song, J.S, Proceedings of the Korean Nuclear Society Spring Meeting, 2007-05 |
| A Rebalance Nonlinear Iteration Method for Solving the Neutron Transport Equations Hong, S.G; Cho, Nam-Zin, Proc. of the International Conference on the Physics of Reactors:Operation, Design and Computation376, 1996-09 |
| A Refined Mechanistic Critical Heat Flux Model for Upflow Boiling at Low Qualities Lee, KW; Chang, Soon-Heung, The 9th International Heat Transfer Conference, Jerusalem, pp.141 - 146, 1990 |
| A Refinement of the Analytic Function Expansion Nodal Method with Interface Flux Moments Woo, S.W; Cho, Nam-Zin; Noh, J.M, Proc. of the Korean Nuclear Society Spring Meeting, v.1, pp.17 -, 1999 |
| A Refinement of the Analytic Function Expansion Nodal Method with Transverse Gradient Basis Functions and Interface Flux Moments Woo, S.W; Cho, Nam-Zin; Noh, J.M, Advances in Reactor Physics and Mathematics and Computation into the Next Millennium (PHYSOR 2000), pp.IX.F.-2 -, 2000-05 |
| A Relaiable Feature Matching Method in Omnidirectional Views for Autonomous Map Generation of a Mobile Robot LEE, Young Jin; Chung, Myung Jin, IEEE/RSJ International Conference on Intelligent Robots and Systems, pp.895 - 900, IEEE Robotics and Automation Society (RAS), 2001-11 |
| A Reliability Estimation Method for Dynamic Systems Which have Various Operation Modes Varying with Time Seong, Poong-Hyun; Shin, Seung Ki; Jang, Inseok; Kang, Hyun Gook, 8th International Topical Meeting on Nuclear Plant Instrumentation, Control and Human-Machine Interface Technologies, pp.308 - 321, ANS, 2012-07-24 |
| A Review for Prediction of Supercritical CO2 Compressor Surge Line Cho, Seong Kuk; Kim, Seong Gu; Lee, Jeong-Ik, The 42nd International Technical Conference on Clean Energy, American Public Power Association, 2017-06-13 |
| A Review of Various Performance Shaping Factors for Use in Advanced Control Rooms 이승우; 하준수; 박재혁; 김자경; 성풍현, 한국원자력학회 2009 추계학술발표회, 한국원자력학회, 2009-10-29 |
| A review on the coupling of CFD code into system code in gas cooled reactor Kim, H.I; No, Hee Cheon, 한국원자력학회 춘계발표회, 한국원자력학회, 2008 |
| A review on the coupling of CFD code into system code in gas cooled reactor No, Hee Cheon, KNS 2008 Spring |
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