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。     

ITER极向场线圈过渡馈线冷屏的结构优化与传热耦合分析

国际热核聚变实验堆磁体馈线系统是连接杜瓦内部的磁体线圈和杜瓦外部之间的冷源、电源以及控制系统的重要通道,其主要作用是为磁体线圈供电、冷却和测量控制诊断。本文通过理论传热计算、利用有限元分析软件ANSYS进行热分析和温度-结构耦合分析,对处于特殊低温与真空环境的辐射冷屏进行了结构优化,保证了系统的安全运行,为降低冷屏热应力和4.5 K温区的热负荷、减小整个系统的热漏指明了方向,为下一轮冷屏结构设计提供了可靠的依据。     

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.     

基于SQL数据库的矿山安全生产信息系统的开发

讨论了基于SQL Sever 2000数据库、B/S模型构建的矿山安全生产信息系统的开发,该系统采用自顶而下、不断迭代和优化的开发策略,能够实时、动态存储和管理安全、生产等信息,并使得这些信息实现共享,提高生产、安全和质量管理的决策科学性与实时处理问题的能力.     

Rapid Thermal-Hydraulic Analysis and Design Optimization of ITER Upper ELM Coils

ITER edge localized mode （ELM） coils are important components of the in-vessel coils （IVCs） and they are designed for mitigating or suppressing ELMs. The coils located on the vacuum vessel （VV） and behind the blanket are subjected to high temperature due to the nuclear heat from the plasma, the Ohmic heat induced by the working current and the thermal radiation from the environment. The water serves as coolant to remove the heat deposited into the coils. Based on the results of nuclear analysis, the thermal-hydraulic analysis is performed for the preliminary design of upper ELM coils using a rapid evaluation method based on 1D treatment. The thermal-hydraulic design and operating parameters including the water flow velocity are optimized. It is found that the rapid evaluation method based on 1D treatment is feasible and reliable. According to the rapid analysis method, the thermal hydraulic parameters of two water flow schemes are computed and proved similar to each other, providing an effective basis for the coil design. Finally, considering jointly the pressure drop requirement and the cooling capacity, the flow velocity is optimized to 5 m/s.     

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.     

托卡马克聚变中子源的数值模型研究

托卡马克(Tokamak)聚变装置中子学分析中,聚变中子源描述是重要的输入参数,其准确性直接影响分析结果的可靠性。通过分析ITER和欧洲聚变示范堆(EU DEMO)中子学分析中所采用的聚变中子源模型,提出了一种完整描述Tokamak中L-mode、H-mode等离子体的D-D、D-T聚变中子源的数值模型。在中国聚变工程实验堆(CFETR)的工程集成设计平台上,编写了基于蒙特卡罗算法的程序SCG求解该数值模型,实现了读取(零维)等离子体参数、输出可供典型中子学软件MCNP直接读取的中子源定义文件的功能。以CFETR氦冷球床包层的中子学分析模型为基准,在相同的L-mode等离子体D-T聚变工况下,相较于采用EU DEMO源子程序,采用本模型计算得到的中子壁负载差异最大值为2.02%,包层氚增殖率差异为0.18%,全堆能量增益因子的差异为0.23%。结果表明,本模型与其他源描述的差异较小,可应用于CFETR的中子学分析。     

ITER线圈终端盒真空隔断的结构设计与分析

真空隔断是真空盒体与低温分配管路之间的连接接口。本文主要介绍了真空隔断的结构设计,并应用有限元分析软件ANSYS Workbench建立了真空隔断的三维实体模型,对其进行了热和结构的耦合分析,获得真空隔断故障态时的应力和温度分布以及传导热。分析的结果为真空隔断的研制提供了可靠的理论依据。