Evolution of the Design of Cold Mass Support for the ITER Magnet Feeder System

This paper presents the evolution of the design of cold mass support for the ITER magnet feeder system. The glass fibers in the cylinder and the flanges of the normal G10 support are discontinuous in the preliminary design. The heat load of this support from the analysis is only 4.86 W. However, the mechanical test of the prototype showed that it can only endure 9 kN lateral force, which is significantly less than the required 20 kN. So, the configuration of the glass fibers in the cylinders and flanges of this G10 support are modified by changing it to a continuous and knitted type to reinforce the support, and then a new improved prototype is manufactured and tested. It could endure 15＇kN lateral forces this time, but still not meet the required 20 kN. Finally, the SS316LN material is chosen for the cold mass supports. The analysis results show that it is safe under 20 kN lateral forces with the heat load increased to 14.8 W. Considering the practical application, the requirements of strength is of primary importance. So, this SS316LN cold mass support is acceptable for the ITER magnet feeder system. On the other hand, the design idea of using continuous and knitted glass fibers to reinforce the strength of a G10 support is a good reference for the case with a lower heat load and not too high Lorentz force.

Conceptual Design and Analysis of Cold Mass Support of the CS3U Feeder for the ITER

In the International Thermonuclear Experimental Reactor（ITER） project,the feeders are one of the most important and critical systems.To convey the power supply and the coolant for the central solenoid（CS） magnet,6 sets of CS feeders are employed,which consist mainly of an in-cryostat feeder（ICF）,a cryostat feed-through（CFT）,an S-bend box（SBB）,and a coil terminal box（CTB）.To compensate the displacements of the internal components of the CS feeders during operation,sliding cold mass supports consisting of a sled plate,a cylindrical support,a thermal shield,and an external ring are developed.To check the strength of the developed cold mass supports of the CS3U feeder,electromagnetic analysis of the two superconducting busbars is performed by using the CATIA V5 and ANSYS codes based on parametric technology.Furthermore, the thermal-structural coupling analysis is performed based on the obtained results,except for the stress concentration,and the max.stress intensity is lower than the allowable stress of the selected material.It is found that the conceptual design of the cold mass support can satisfy the required functions under the worst case of normal working conditions.All these performed activities will provide a firm technical basis for the engineering design and development of cold mass supports.

15W@80K全气体轴承室温活塞脉管制冷机研发

为了满足超大规格线列、面阵红外探测器及红外光学系统对大冷量、长寿命、低振动、紧凑化、高效率及轻型低温制冷机的需求,开展了15 W@80 K全气体轴承室温活塞脉管制冷机研发,采用Sage热力学软件进行了仿真分析,设计了首款基于全气体轴承支撑和室温活塞功回收技术的斯特林脉管制冷机,成功完成了工程样机研制并进行了性能测试。测试结果表明,散热流体温度20℃,制冷温度为80 K,制冷机在交流输入功率为320 W时,制冷量达到22 W,制冷效率达到6.875%;输入电功为397.9 W时,制冷量达到26.16 W,制冷效率为6.56%,冷量质量比(制冷量/质量)为3.1W/kg。散热流体温度20℃,制冷温度为60 K,制冷机在交流输入功率为360 W时,制冷量达到14 W,制冷效率为3.91%;制冷机在交流输入功率为400 W时,制冷量达到15.46 W,制冷效率为3.86%。验证了室温活塞调相技术的先进性,样机性能参数满足项目技术指标要求。

1.5TMRI超导磁体低温容器的拉杆设计与校核

1.5TMR I磁体系统冷重约为4吨,为提高该系统稳定性,采用环氧跑道拉杆结构。分析了磁体正常运行时拉杆上承受的重力、冷缩力,运输过程中的动载力,以及拉杆安装过程中施加的预紧力。在分析的基础上,对拉杆的材料、安装角度进行了选取,并结合漏热对横截面积进行了优化。

FAIR二极超导磁体样机结构稳定性的初步研究

冷质部件的支撑是FAIR二极超导磁体样机中的关键部件,它们对于保持线圈的空间位形起到至关重要的作用,因此,对其开展稳定性的研究是十分必要的。为此,文中基于压杆稳定的理论和有限元法,对支撑进行了稳定性的研究,为支撑力学性能的评估、结构的优化设计和磁体样机的工程设计提供了参考依据。

ITER校正场过渡馈线冷质支撑的设计与传热分析

对过渡馈线的冷质支撑在真空与低温环境下的绝热性能进行研究,以增大热阻抑制热量传递为目的,在保证强度的基础上,同时考虑加工与装配的方便,确定了一种支撑结构。并利用有限元方法对该结构进行了稳态传热分析,得出了支撑的温度分布和冷量损耗大小。研究表明该支撑在满足强度的要求下,不仅结构简单、装配方便而且绝热性能良好,能很好地降低ITER制冷系统的热负载。

ITER馈线系统冷质支撑的设计和静力学分析

国际热核聚变反应堆ITER是多个国家合作的项目,目的是建造一个大型的可控核反应系统,而ITER馈线系统中的冷质支撑件是系统稳定运行的保障。为了设计出符合工程要求的部件,主要以冷质支撑的强度设计要求为基准点,从支撑结构的确立到材料的选择等方面详细阐述了冷质支撑的设计过程,并利用有限元分析软件ANSYS对其静载荷下的主要零部件的力学性能进行了分析,从理论上论证了这种结构设计方案的科学性与可行性。

ITER真空绝热冷质支撑性能测试平台设计与研究

真空绝热冷质支撑(cold mass support,CMS)是国际热核聚变反应堆(International Thermonuclear Fusion Reactor,ITER)中的关键支撑部件之一。为了检测已制造完成的冷质支撑的性能是否达到合格验收标准,在交付前需对它进行摩擦性能测试和机械强度测试。通过分析复杂工况下冷质支撑的受载特点,结合摩擦测试标准ASTM D1894-14和摩擦力的工程计算结果,设计了冷质支撑摩擦性能测试平台。基于冷质支撑的受载工况,先初步设计了冷质支撑机械强度测试平台,并通过弯矩梁的受力分析确定了10号工字钢为弯矩梁的最佳材料,再利用液压伺服装置对冷质支撑施加工况载荷,完成了冷质支撑机械强度测试平台相关设备和工装的结构设计。考虑到单独实施摩擦性能测试和机械强度测试的各项成本,结合2项测试的特点,设计了冷质支撑性能一体化测试平台。结果表明冷质支撑性能一体化测试平台能够有效缩短测试周期和降低检测成本,可为冷质支撑的工程质量认证及后续批量生产提供保障。