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For China helium cooled ceramic breeder test banket module (CH HCCB TBM), a new structure with 1×4 configuration is proposed. Based on this new structure proposal, the detail structural design for the sub-module and its complicated back plate has been performed, also the preliminary pressure analysis for the back plate of sub-module has been finished.     

方管锂铅磁流体氚增殖剂中的氚输运模拟

利用COMSOL Multiphysics软件实现磁场、导电流体、氚输运的多物理场耦合,研究了在强磁场下3维方管中锂铅流体内的氚输运及其分布。通过计算得到,锂铅流体在平行磁场方向的导电壁侧形成了射流,而在哈德曼壁侧及流体的芯部区域流动滞缓;射流的强对流效应使得在导电壁侧具有较低的氚浓度,而在哈德曼壁面侧及流体芯部具有较高的氚浓度累积,形成了不对称的氚浓度体分布。     

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Based on the CH HCCB TBM design, the detail of the new modified first wall (FW) was described, and a series related analysis was conducted to compare with former design. In the preliminary analysis, the modified FW design shows much more advantages in comparison with the former design. The working conditions of the analysis have been set to ITER design condition. The performances and the results obtained from thermo-hydraulics and stress analysis are presented.     

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The helium loop was designed and constructed to the testing of various components for nuclear fusion facilities. The loop contains diaphragm circulator, electrical heater, helium recuperator, water-helium heat exchanger and storage tank etc. The test section helium inlet parameters are pressure 8MPa, temperature 300?棬and flow rate 0.1kg•s^-1. These parameters fulfill small components testing requirements.     

中国超导聚变工程实验堆氦冷固态包层中子学设计分析

根据中国聚变工程实验堆(CFETR)设计要求,参考氦冷固态包层实验包层模块(HCCB TBM)的设计经验,完成了CFETR固态包层的中子学设计分析,并评估了中平面位置可开窗口的最大面积。设计分析结果表明,基于增殖单元的固态包层中子学设计方案的氚增殖比(TBR)达到了1.243,满足CFTER氚自持设计要求;中平面可以开出的辅助窗口的最大面积为11.43m²。     

铜导体CFETR氦冷固态包层及屏蔽中子学设计与分析

根据铜导体CFETR设计要求,对铜导体CFETR固态包层和屏蔽进行了中子学设计与分析,提出了套管结构的氦冷固态包层设计方案。包层设计和屏蔽分析结果表明,基于套管的氦冷固态包层的氚增殖比(TBR)达到了1.25, 满足铜导体CFTER氚自持设计要求;环向场线圈绝缘层在堆寿期内不会出现显著的辐射感应电导率(RIC)与辐射引起的电气性能退化(RIED)效应。     

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In the present work, tritium permeation issue of gas injection system (GIS) in DEMO were focused. Based on the reactor core parameters of Chian Fusion Engineering Test Reactor (CFETR) and referring to accumulated experience of GIS design in ITER, preliminary pipes layout of DEMO GIS was performed. Steady-state tritium gas pressure drop calculation along the pipes and pump head request to the fuel storage and delivery system were made on the basis of the GIS’s structure layout. Tritium permeation under corresponding pump head was calculated at the same time. According to the calculation results, gravitational potential is the main determinant to pressure drop in pipe flow and the tritium permeation in GIS is of little amount to the whole tritium cycle in the case negative pressure. So this work offers related parameters to tritium self-sufficiency issues in DEMO, and also lays the foundation for further optimization of GIS’s structure layout.