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《Chinese Journal of Nuclear Science and Engineering》 2010-01
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Neutronics design and analysis of water-cooled energy production blanket for a fusion-fission hybrid reactor

JIANG Jie-qiong1.2,WANG Ming-huang1.2,CHEN Zhong1.2,QIU Yue-feng1.2,LIU Jin-chao1.2,WU Yi-can1.2,FDS Team1.2(1.Institute of Plasma Physics,Chinese Academy of Sciences,Hefei of Anhui Prov.230031,China;2.School of Nuclear Science and Technology,University of Science and Technology of China,Hefei of Anhui Prov.230027,China)  
Neutronics calculations were performed to analysis the parameters of blanket energy multiplication factor(M) and tritium breeding ratio(TBR) in a fusion-fission hybrid reactor for energy production named FDS-EM(Energy Multiplier) blanket.The most significant and main goal of the water-cooled FDS-EM blanket is to achieve the energy gain of about 1 GW with self-sustaining tritium,which can operate for as long as possible without fuel unloading and reloading.The preliminarily designed neutronics parameters for FDS-EM were presented,which show that the blanket loaded with the Nuclear Waste(transuranic from 33 000 MWD/MTU PWR and depleted uranium) for energy multiplication(M≈90) with tritium self-sufficiency can operate for at least 10 years without fuel unloading and reloading.
【Fund】: 中科院知识创新工程重要方向项目;; 中科院重大科学装备;; ITER计划专项项目
【CateGory Index】: TL64
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