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1 K.I. Ahn, J.E. Yang, and J.J. Ha, 'The Plant-specific Impact of Different Pressurization Rates in the Probabilistic Estimation of Containment Failure Modes,' Journal of the Korean Nuclear Society, Vol.35 (2), pp.154-164 (April 2003)/ View Article
2 K.I. Ahn and J.E. Yang, 'The Explicit Treatment of Model Uncertainties in the Presence of Aleatory and Epistemic Parameter Uncertainties in Risk and Reliability Analysis,' Journal of the Korean Nuclear Society, Vol.35 (1), pp.64-79 (February 2003)/   KOI View Article
3 Kim S.O. et aI, 'Evaluation of New Design Concepts for Steam Generators in Sodium Cooled Liquid Metal Reactor' , J. of KNS, Vol.35, No.2, pp.121-132, April (2003)/ View Article
4 Sim Y.S. et aI, 'A New LMR SG with a Double Tube Bundle Free from SWR', J. of KNS, Vol.35, No.6, pp. 571-591, Dec.(2003)/   KOI View Article
5 H-Y Hwang, S. I. Kwak, Y.H Cho, J.I. Byun, HY Lee, J.S. Seo, J.Y. Kwak, J.M. Lee, K.B. Lee, T.S. Park, K.H. Chung and C. W. Lee, J. of Korean Nuclear Society 35 165(2003)/   KOI View Article
6 J. W. Park, C. L. Kim, J. B. Park and E. Y. Lee, 'Development of a Quality Assurance Safety Assessment Database for Near Surface Radioactive Waste Disposal', J. Korean Nuclear Society, Vol. 35, No.6, pp. 556-565, Dec. 2003/   KOI View Article
7 Kwang W. Seul, et al., Simulation of Multiple Steam Generator Tube Rupture (SGTR) Event Scenario, Journal of KNS, Vol. 35, No.3, pp 179-190, June (2003)/   KOI View Article
8 Jo, J.C., Jhung, M.J., Kim, W.S., Choi, Y.H., Kim, H.J., and Kim, T.H., 2003, 'Fretting-wear characteristics of steam generator tubes by foreign object,' Journal of the Korean Nuclear Society, Vol.35, No.5, pp.442-453/   KOI View Article
9 J. H. Song et. al., Spontaneous steam explosions observed in the fuel coolant interaction experiments using reactor materials, Journal of Korean Nuclear Society, Vol. 33(4), 344-357, 2002/   KOI View Article
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