Experimental investigation on molten pool representing corium composition at Fukushima Daiichi nuclear power plant
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Jin Ho Song | Masanori Naitoh | Hwan-Yeol Kim | Sang Mo An | J. Song | S. An | H. Kim | Jong-Yun Kim | M. Naitoh | Jong-Yun Kim
[1] Beverly A. Cook,et al. Materials Interactions and Temperatures in the Three Mile Island Unit 2 Core , 1989 .
[2] Kwang Soon Ha,et al. EVALUATION OF HEAT-FLUX DISTRIBUTION AT THE INNER AND OUTER REACTOR VESSEL WALLS UNDER THE IN-VESSEL RETENTION THROUGH EXTERNAL REACTOR VESSEL COOLING CONDITION , 2015 .
[3] O. Kymäläinen,et al. In-vessel coolability and retention of a core melt , 1997 .
[4] Nuclear Emergency Response Headquarters. Report of Japanese Government to the IAEA Ministerial Conference on Nuclear Safety : the Accident at TEPCO's Fukushima Nuclear Power Stations , 2011 .
[5] P Hofmann,et al. Current knowledge on core degradation phenomena, a review , 1999 .
[6] Tae Woon Kim,et al. SEVERE ACCIDENT ISSUES RAISED BY THE FUKUSHIMA ACCIDENT AND IMPROVEMENTS SUGGESTED , 2014 .
[7] Jean-Marie Seiler,et al. Theoretical Analysis for Corium Pool with Miscibility Gap , 2003 .
[10] Jin Ho Song,et al. Application of cold crucible for melting of UO2/ZrO2 mixture , 2003 .
[11] B. Min,et al. A physical and chemical analysis of fast quenched particles of UO2 and ZrO2 mixture , 2006 .