Numerical research on the neutronic/thermal-hydraulic/mechanical coupling characteristics of the optimized helium cooled solid breeder blanket for CFETR

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• 作者：Shijie Cui ; Dalin Zhang ; ^{dlzhang@mail.xjtu.edu.cn} ; Jie Cheng ; Wenxi Tian ; G.H. Su
• 关键词：CFETR ; Blanket ; Coupling analysis ; Neutronics ; Thermal-hydraulics ; Thermo-mechanics
• 刊名：Fusion Engineering and Design
• 出版年：2017
• 出版时间：January 2017
• 年：2017
• 卷：114
• 期：Complete
• 页码：141-156
• 全文大小：5564 K
• 卷排序：114

文摘

As one of the candidate tritium breeding blankets for Chinese Fusion Engineering Test Reactor (CFETR), a conceptual structure of the helium cooled solid breeder blanket has recently been proposed. The neutronic, thermal-hydraulic and mechanical characteristics of the blanket directly affect its tritium breeding and safety performance. Therefore, neutronic/thermal-hydraulic/mechanical coupling analyses are of vital importance for a reliable blanket design. In this work, first, three-dimensional neutronics analysis and optimization of the typical outboard equatorial blanket module (No. 12) were performed for the comprehensive optimal scheme. Then, thermal and fluid dynamic analyses of the scheme under both normal and critical conditions were performed and coupled with the previous neutronic calculation results. With thermal-hydraulic boundaries, thermo-mechanical analyses of the structure materials under normal, critical and blanket over-pressurization conditions were carried out. In addition, several parametric sensitivity studies were also conducted to investigate the influences of the main parameters on the blanket temperature distributions. In this paper, the coupled analyses verify the reasonability of the optimized conceptual design preliminarily and can provide an important reference for the further analysis and optimization design of the CFETR helium cooled solid breeder blanket.