Impact analysis of the time trend of TBR and irradiation damage assessment of HCSB blanket for CFETR

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• 作者：Qin Zeng ; ^{zengqin@ustc.edu.cn} ; Hongli Chen ; Zhongliang Lv ; Lei Pan ; Haoran Zhang ; Wei Shi
• 关键词：Helium cooled solid breeder blanket ; the time trend of TBR ; Irradiation damage ; 3D neutronics model
• 刊名：Fusion Engineering and Design
• 出版年：2017
• 出版时间：January 2017
• 年：2017
• 卷：114
• 期：Complete
• 页码：52-56
• 全文大小：1288 K
• 卷排序：114

文摘

Chinese Fusion Engineering Testing Reactor (CFETR) is a test tokamak reactor to bridge the gap between ITER and future fusion power plants and to demonstrate generation of fusion power in China. In fusion power plants, tritium is generated from the reaction of neutron and Lithium. One of the missions of CFETR is the full cycle of tritium self-sufficiency. For the mission, a Helium Cooled Solid Breeder blanket (HCSB) was proposed for CFETR and its conceptual design has been carried out. In order to assess the capacity of the tritium breeding and irradiation damage of first wall of the HCSB blanket during the 8 years’ engineering test stage, this paper presents the time trend of TBR analysis and irradiation damage assessment of HCSB blanket based on the three-dimensional (3D) neutronics model which is created by McCad. In the 3D neutronics model, the outboard blanket on equatorial plane is described based on the detailed 3D engineering model. The calculations were performed by MCNP and FISPACT with FENDL/2.1 data library. The impact analysis of the thickness of coolant plates (CP) and the structural material content in CPs to the TBR is assessment.