ITER用316LN激光焊接接头显微组织和力学性能研究

以21 mm厚的316LN奥氏体不锈钢板为研究对象,采用双面对称施焊的方式进行激光焊接,并对激光焊接接头的显微组织和力学性能进行了分析。结果表明,采用锁底式打底焊接时,焊缝中的主要缺陷是焊接气孔。减小钝边厚度,采用单面打底焊后,气孔问题得到解决。焊缝区显微组织为单相奥氏体,不同位置的显微组织呈现不同的结晶形态,焊缝中心处的等轴晶粒能有效抑制焊接裂纹的产生。激光焊焊接接头拉伸试样均断裂于母材处,弯曲样件表面未见任何微裂纹,焊接接头展现了良好的抗低温冲击性能。     

HT-7U真空室支撑结构的数值模拟与实验研究

结合HT-7U超导托卡马克装置真空室的实际运行工况,首先提出一种低刚度柔性支撑结构,这种结构不仅有足够的强度,抵抗由于等离子体突然破裂产生的巨大电磁力,而且还有一定的弹性,吸收真空室在250℃壁处理烘烤时所产生的热变形。然后运用有限元分析方法对该结构的力学性能进行数值模拟分析,获得HT-7U真空室支撑结构的应力云图,最大应力为97MPa,小于结构基体材料316L不锈钢的许用应力。同时还专门设计一套真空室支撑结构力学实验测试平台,利用光弹贴片法和电阻应变计测量法,对该结构进行全面的力学性能测试,不仅验证有限元分析结果的可信件,而且还寸步证实HT-7U真空室支撑结构设计的合理性和安全性。     

ITER内馈线支承系统的结构设计与分析

馈线系统是国际热核聚变实验反应堆ITER(International Thermonuclear ExperimentalReactor)上的重要装置,任务是向磁体线圈传输电流和冷却液,并对磁体系统进行测量、控制和诊断.位于杜瓦内部的内馈线是馈线系统的一部分,工作于低温、强磁场环境,由悬挂支承系统将其固定于纵向场磁体线圈终端.详细阐述了内馈线支承系统的结构设计方案,通过有限元运算获得了内馈线部分的应力和位移分布情况.结果显示最大应力强度为160MPa,最大位移变形为0.618mm.分析结果为装置的结构优化与最终研制提供了理论依据.     

EAST液态锂试验测试平台磁体系统的MATLAB辅助设计

为了设计一套液态锂台面试验测试平台磁体系统,并保证磁体线圈的安全稳定运行,采用了MATLAB对其进行辅助设计,并对计算结果进行了校核计算。通过对线圈产生的磁场及其电参数和水参数的计算,可知:线圈的安匝数、线圈半径等对线圈磁场的分布、冷却水的流速及平台的综合成本具有显著的影响。计算结果对于磁体线圈的参数设计,以及冷却水泵和电源的选型具有重要的指导意义。     

Static and Dynamic Mechanical Analyses for the Vacuum Vessel of EAST Superconducting Tokamak Device

EAST （experimental advanced superconducting tokamak） is an advanced steadystate plasma physics experimental device, which is being constructed as the Chinese National Nuclear Fusion Research Project. During the plasma operation the vacuum vessel as one of the key component will withstand the electromagnetic force due to the plasma disruption, the Halo current and the toroidal field coil quench, the pressure of boride water and the thermal load due to 250℃ baking by pressurized nitrogen gas. In this paper a report of the static and dynamic mechanical analyses of the vacuum vessel is made. Firstly the applied loads on the vacuum vessel were given and the static stress distribution under the gravitational loads, the pressure loads, the electromagnetic loads and thermal loads were investigated. Then a series of primary dynamic, buckling and fatigue life analyses were performed to predict the structure＇s dynamic behavior. A seismic analysis was also conducted.     

基于SYSWELD的CTB&SBB真空壳体的焊接仿真分析

国际热核实验反应堆ITER计划是研究可控核聚变的一个大型国际研究合作项目.线圈终端盒(CTB)和S弯盒(SBB)是保证ITER装置可靠运行的关键部件之一,作用是为磁体系统与其他系统相联接提供接口和屏蔽保护.其外壳则要为CTB和SBB的内部部件提供真空环境.因此壳体的焊接品质直接影响着装置的安全稳定运行.本文利用双椭球热源模型,采用有限元分析软件SYSWELD,对CTB&SBB外壳原型件的MIG焊接工艺进行了仿真数值模拟,得到其变形及残余应力值.分析结果表明,此MIG焊接工艺适合CTB&SBB真空壳体的焊接.     

A Lower Rigid Support Structure for the HT—7U Vacuum Vessel

Vacuum vessel of the HT-7U is a fully welded toroidal structure with a noncircularcross-section nested in the bore of the TF coils. According to the requirement of the physicsdesign, sixteen horizontal ports on outboard mid-plane and thirty-two vertical ports on the topand bottom are designed for diagnostics, plasma heating, current driving, vacuum pumping andgas puffing. Bellows on these port necks are used for flexible components to absorb the relativedisplacement in radial and vertical directions due to external load, thermal expansion or contrac-tion and assembly tolerance, and also used for isolation of mechanical vibration. For the supportsystem of vacuum vessel it should be not only strong enough to withstand forces acting on thevessel interior components and the vessel itself due to the dead weight and electromagnetic inter-actions during plasma disruption, but also sufficiently flexible to be suited to thermal expansionduring baking. In order to solve this contradiction a new kind of low rigid s     

采用辐射变色薄膜的束流位置诊断研究

依据SC200超导质子回旋加速器的束流特性及调试需求,在质子束加速及引出的过程中需精确测量主机束流的位置信息。提出了采用辐射薄膜进行加速器束流位置诊断的方法,通过剂量计算得到了不同测量位置的薄膜最佳使用类型,借助测试平台对所有选型的薄膜进行实验验证。为优化薄膜的辐照变色效果,结合剂量及实验分析给出了不同测量位置的最佳照射时间。完成了所测位置的薄膜固定装置设计,并提出将薄膜变色区域可视化得束流位置信息的处理方案。     

Design,Analysis and R＆D of the EAST In-Vessel Components

In-vessel components are important parts of the EAST superconducting tokamak. They include the plasma facing components, passive plates, cryo-pumps, in-vessel coils, etc. The structural design, analysis and related R＆D have been completed. The divertor is designed in an up-down symmetric configuration to accommodate both double null and single null plasma operation. Passive plates are used for plasma movement control. In-vessel coils are used for the active control of plasma vertical movements. Each cryo-pump can provide an approximately 45 m^3/s pumping rate at a pressure of 10^-1 Pa for particle exhaust. Analysis shows that, when a plasma current of 1 MA disrupts in 3 ms, the EM loads caused by the eddy current and the halo current in a vertical displacement event （VDE） will not generate an unacceptable stress on the divertor structure. The bolted divertor thermal structure with an active cooling system can sustain a load of 2 MW/m^2 up to a 60 s operation if the plasma facing surface temperature is limited to 1500 ℃. Thermal testing and structural optimization testing were conducted to demonstrate the analysis results.