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《Chinese Journal of Nuclear Science and Engineering》 2011-01
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Design analysis of a new SCWR fuel assembly using a coupled method

LIU Xiao-jing,YANG Ting,CHENG Xu(School of Nuclear Science and Engineering,Shanghai Jiao Tong University,Shanghai 200240,China)  
Among the six GEN-Ⅳ reactor concepts recommended by the Gen-Ⅳ International Forum(GIF),supercritical water-cooled reactor(SCWR) is the only reactor type with water as coolant.Compared to the existing reactors,it has economic advantage and technology continuity.Based on the newly developed coupling code,analysis on the square SCWR assembly is carried out in this paper.A new design concept of SCWR fuel assembly is proposed.The results achieved so far indicate favorable thermal-hydraulic performance and neutron-physical behavior of the new fuel assembly compared to the previous ones.
【Fund】: “973计划”项目资助(No.2007CB209804)
【CateGory Index】: TL352
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