Showing results 2461 to 2480 of 5608
Fast and reliable phasor detectors for single phase AC systems by derivative quadrature generation Rim, Chuntaek; Choi, Bohwan; Lee, Sungwoo; Yeo, Inyong, IPEMC2012-ECCE Asia, IEEE, 2012-06 |
FAST and SAFE Passive Safety Devices for Sodium-cooled Fast Reactor Hartanto, Donny; 김치형; 김용희, The Korean Nuclear Society Spring Meeting(2015), The Korean Nuclear Society Spring, 2015-05-08 |
Fast Core Prediction Simulator for Load Follow Control Yim, Man-Sung; Lee, SangHoon; Lee, Un Chul, 1990 Annual Spring Conference, Korean Nuclear Society, no.1990, Korean Nuclear Society, 1990-05 |
Fast neutron detection utilizing pile-up rejection and PSD for homeland security Lee, Sangho; Song, Gyohyeok; Kim, Hojik; Kim, Junhyeok; Ko, Kilyoung; Hwang, Jisung; Ko, Eunbi; et al, 2022 IEEE Nuclear Science Symposium, Medical Imaging Conference and Room Temperature Semiconductor Detector Conferenc, IEEE NPSS, 2022-11-09 |
Fast neutron measurement for homeland security using PSD of neutrons and X-rays generated by LINAC Song, Gyohyeok; Lee, Sangho; Hwang, Jisung; Kim, Junhyeok; Ko, Kilyoung; Park, Jaehyun; Cho, Gyuseong, 23rd International Workshop on Radiation Imaging Detectors, iWoRiD 2022, CERN, 2022-06-29 |
Fast Neutron-Gamma Pulse Shape Discrimination (PSD) in the Plastic Scintillator EJ-200 김민환; 김진환; 임경택; 김기윤; 고길영; 조규성, 한국방사선산업학회, 한국방사선산업학회, 2019-11-06 |
Fast Running System Code Development with Analytical Solution Technique and Marching Scheme Whang, DH; Lee, BH; Chang, Soon-Heung, '85 ANS National Heat Transfer Conference, pp.141 - 150, ANS, 1985-08 |
Fast Solution of Linear Systems by Wavelet Transform Park, C.J; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Spring Meeting, v.1, pp.282 - 287, 1996-05 |
Fatigue Crack Growth and Fracture Resistance of the Stainless Steel Narrow Gap Welds in Nuclear Piping System Jang, Changheui, 7th ASINCO, 2008-07-03 |
Fatigue crack growth of SA508 Cl.3 pressure vessel steel in high-temperature argon and water environments Kim, In Sup; Lee S.O.; Cho H.C., Sixth International Conference on Computer Methods and Experimental Measurements for Surface Treatment Effects, Surface Treatment VI, v.7, pp.277 - 284, 2003-03-11 |
Fatigue Crack Propagation Behavior in Butt Weldment of SA106Gr.C Main Steam Pipe Steel 김인섭, Proc. of the Korean Nuclear Society Spring Meeting, pp.92 - 97, 1996 |
Fatigue effect of RCS branch line by thermal stratification Youm H.-K.; Kim K.-C.; Park M.-H.; Jin T.-E.; Lee S.-K.; Kim T.-R.; Kim, Jong Hyun, 2003 ASME Pressure Vessels and Piping Conference, v.454, pp.61 - 67, 2003-07-20 |
Fatigue Life Evaluation of Major Components for Nuclear Power Plant Lifetime Management Jang, Changheui, 14th International Conference on Structural Mechanics in Reactor Technology, 1997-08-20 |
Fatigue Properties of Inconel 690 Steam Generator Tubing Materials 김인섭, Conference on Mechanical Behavior of Materials, pp.303 - 312, 1998 |
Fatigue Test and Life Estimation of Incoloy 908 Jang, Changheui, Advances on Cryogenic Engineering, 1996-07-15 |
Fault tolerance evaluation of digital plant protection system in nuclear power plants Lee, J.S.; Kim, M.C.; Seong, Poong-Hyun; Kang, H.G.; Jang, S.C., 2005 Annual Meeting - American Nuclear Society, v.92, pp.411 - 412, 2005-06-05 |
Fault Tree Analysis with Temporal Gates and Model Checking Technique for Qualitative System Safety Analysis 고광용; 성풍현, 한국원자력학회 2010 춘계학술발표대회, 한국원자력학회, 2010-05-28 |
Fault Tree Model of Human Error Based on Error-Forcing Contexts Kang, Hyun Gook; Jang, Seung-Cheol; Ha, Jae-Joo, 한국원자력학회 2004년도 추계학술발표회 , pp.587 - 588, 한국원자력학회, 2004-10-29 |
Fault tree synthesis for software design analysis of PLC based safety-critical systems Koo, S.-R.; Cho, C.-H.; Seong, Poong-Hyun, 5th International Topical Meeting on Nuclear Plant Instrumentation Controls, and Human Machine Interface Technology (NPIC and HMIT 2006), pp.148 - 153, 2006-11-12 |
Fault Tree-based Software Safety Analysis of Function Block Diagrams Koh, KY; Seong, Poong-Hyun, ISSNP 2007, 2007-07-23 |
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