Browse "Dept. of Nuclear and Quantum Engineering(원자력및양자공학과)" by Title
Showing results 4701 to 4720 of 10376
| Fast running system code development with analytic solution technique and marching scheme = 해석적 해법과 마칭 방법에 의한 고속 시스템 코드의 개발link Hwang, Dae-Hyun; 황대현; et al, 한국과학기술원, 1985 |
| 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 signal transfer in a large-area X-ray CMOS image sensor Kim, M. S.; Kang, D. U.; Lee, D. H.; Kim, H.; Cho, Gyuseong; Jae, M., JOURNAL OF INSTRUMENTATION, v.9, 2014-08 |
| Fast singular value decomposition combined maximum entropy method for plasma tomography Kim, Jung-Hee; Choe, Wonho, REVIEW OF SCIENTIFIC INSTRUMENTS, v.77, no.2, pp.115 - 117, 2006-02 |
| 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 |
| Fast uranium enrichment measurement in very low-level wastes by using a neural network algorithm = 신경망 알고리즘을 이용한 극저준위 폐기물 고속 우라늄 농축도 분석link Ryu, Jichang; Cho, Gyuseung; et al, 한국과학기술원, 2021 |
| Fate of the peak effect in a type-II superconductor: Multicriticality in the Bragg-glass transition Park, SR; Choi, SungMin; Dender, DC; Lynn, JW; Ling, XS, PHYSICAL REVIEW LETTERS, v.91, no.16, 2003-10 |
| 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 pressure vessel steel in high temperature water environment = 고온수화학 분위기에서 압력용기강의 피로균열 성장link Lee, Sang-Gyu; 이상규; et al, 한국과학기술원, 2001 |
| 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 deformation of microsized metallic glasses Jang, Dongchan; Maass, Robert; Wang, Gongyao; Liaw, Peter K.; Greer, Julia R., SCRIPTA MATERIALIA, v.68, no.10, pp.773 - 776, 2013-05 |
| 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 and crack growth mechanisms of the type 316LN austenitic Stainless Steel in 310 degrees C deoxygenated water Cho, Hyunchul; Kim, Byoung Koo; Kim, In Sup; Jang, Changheui; Jung, Dae Yul, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, v.44, no.7, pp.1007 - 1014, 2007-07 |
| 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 DETECTION COVERAGE QUANTIFICATION OF AUTOMATIC TEST FUNCTIONS OF DIGITAL IC SYSTEM IN NPPS Choi, Jong Gyun; Lee, Seung Jun; Kang, Hyun Gook; Hur, Seop; Lee, Young Jun; Jang, Seung Cheol, NUCLEAR ENGINEERING AND TECHNOLOGY, v.44, no.4, pp.421 - 428, 2012-05 |
| 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., TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, v.92, no.0, pp.411 - 412, 2005 |
| 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 |
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