HELIMAK装置真空室结构设计及应力强度分析

HELIMAK装置真空室作为该装置的重要部件,是等离子体运行的直接场所,在装嚣运行期问町以为等离子体的运行提供一种超高真空运行环境。对于此类核聚变装置的结构设计,必须考虑运行时的实际工况载荷,进行详细的结构力学分析,使结构设计充分安全可靠。文中首先借用大犁有限元分析程序NASTRAN,对该结构的力学性能进行数值模拟分析,获得了HELIMAK真空室的应力云图和位移变形,最大应力强度为144MPa,最大何移变形为1．98mm。然后在力学分析的基础上对结构进行优化,为该装置的最终研制提供详实的理论依据。     

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。     

ITER终端盒结构设计

终端盒是国际热核聚变实验堆(ITER)磁体系统的重要组成部分,这里介绍了ITER终端盒的结构设计,并采用有限元法对终端盒关键部件进行校核和应力分析,为结构的进一步研制提供了理论依据。     

核聚变装置放电真空室材料的要求和发展

通过回顾托马克构核聚变实验装置的发展历程和放电真空室及内部部件材料的运用历史,联系近些年国内外一些托马克装置的最新实验结果,对不锈钢、钛合金、纤维增强的复合材料在放电真空室上的应用进行展望,为未来核聚变实验装置的工程设计和材料选择提供了依据。     

ITER校正场线圈过渡馈线真空隔断传热及热应力分析

ITER校正场线圈馈线系统的真空隔断是过渡馈线中的重要组成部分,位于S弯盒与过渡馈线的接口处,用以保证S弯盒和过渡馈线中不同真空系统的独立性,便于系统维护.针对真空隔断的作用,介绍了其设计结构,使用ANSYS软件建立了真空隔断的热及结构有限元模型,考虑到热传导、热辐射及外部自然对流对真空隔断工作环境的影响,计算了其温度分布、低温区的热载及其热应力,结果验证了真空隔断结构设计的可行性,为真空隔断的进一步优化及试制奠定基础.     

ITER超导接头铜材热损耗实验研究

为了评估ITER超导接头所采用的铜材的热损耗影响,设计并搭建了用于测试剩余电阻率的实验平台。通过对所选用的铜材进行低温4.2 K和常温下的电阻率测试,计算了铜材的剩余电阻率。结果表明,所选用的铜材能够满足ITER双盒搭接接头铜材的设计要求。     

反场箍缩装置KTX真空室结构稳定性分析

KTX为中国科学技术大学在建的反场箍缩实验装置,在同类装置之间,其参数介于美国MST和意大利的RFX之间。KTX真空室壁厚仅为6 mm,属于非标准环形薄壳结构,其结构的稳定性分析是确定结构设计是否合理的关键因素。本文利用有限元的方法,对KTX真空室结构进行了线性和非线性屈曲分析。得到了两种情形下应力和变形加载曲线。通过对计算结果的对比和分析,验证了目前真空室结构的稳定性符合要求,并具有一定的安全裕度。     

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     

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.