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采用20kW超高功率光纤激光器单道焊接了20mm厚316LN奥氏体不锈钢,研究了焊接工艺参数对焊缝成形及宏观形貌的影响,并对焊接接头的显微组织和力学性能进行了分析。结果表明,采用负离焦可以得到成形良好的焊缝;焊缝组织为单一的奥氏体组织,焊缝上部和底部中心区存在等轴晶粒,焊缝中部中心区为粗大的柱状晶。在优化的工艺参数下,焊接得到的接头抗拉强度为645 MPa,与母材相当。焊接接头断裂于熔合线边界处,为典型的韧性断裂。焊接接头热影响区的显微硬度略高于焊缝和母材。 相似文献
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The ion cyclotron resonance of frequency heating(ICRH) plays an important role in plasma heating.Two ICRH antennas were designed and applied on the EAST tokamak.In order to meet the requirement imposed by high-power and long-pulse operation of EAST in the future,an active cooling system is mandatory to be designed to remove the heat load deposited on the components.Thermal analyses for high heat-load components have been carried out,which presented clear temperature distribution on each component and provided the reference data to do the optimization.Meanwhile,heat pipes were designed to satisfy the high requirement imposed by a Faraday shield and lateral limiter. 相似文献
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杨宇晴 张新军 赵燕平 秦成明 程艳 毛玉周 杨桦 王健华 袁帅 王磊 琚松青 陈根 邓旭 张开 万宝年 李建刚 宋云涛 龚先祖 钱金平 张涛 《等离子体科学和技术》2018,20(4):45102-111
Recent ion cyclotron resonance frequency(ICRF) coupling experiments for optimizing ICRF heating in high power discharge were performed on EAST. The coupling experiments were focus on antenna phasing and gas puffing, which were performed separately on two ports of the ion cyclotron resonance heating(ICRH) system of EAST. The antenna phasing was performed on the I-port antenna, which consists of four toroidally spaced radiating straps operating in multiple phasing cases; the coupling performance was better under low wave number ∣k_‖∣(ranging from 4.5 to 6.5). By fuelling the plasma from gas injectors, placed as uniformly spaced array from top to bottom at each side limiter of the B-port antenna, which works in dipole phasing, the coupling resistance of the B-port antenna increased obviously.Furthermore, the coupling resistance of the I-port antenna was insensitive to a smaller rate of gas puffing but when the gas injection rate was more than a certain value(1021 s~(-1)), a sharp increase in the coupling resistance of the I-port antenna occurred, which was mainly caused by the toroidal asymmetric boundary density arising from gas puffing. A more specific analysis is given in the paper. 相似文献
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基于中国聚变工程实验堆(Chinese Fusion Engineering Testing Reactor,CFETR)提出了一种新型氦冷固态氚增殖包层设计方案。以托卡马克中平面上一块外包层模块为例,系统介绍了该包层概念设计。基于工程流体力学理论,对包层模块内冷却剂的流动特性进行了理论求解。同时采用计算流体动力学(Computational Fluid Dynamics,CFD)软件CFX,对包层模块流体域和固体域进行耦合传热分析,求解得到冷却剂的流动特性和理论计算难以求解的固体域温度场分布。计算结果表明:理论计算与模拟结果吻合程度良好,冷却剂在包层内总压降为243 k Pa,总温升为194.6°C,运行在合理区间;包层各结构材料在正常运行工况下的温度可以满足材料的最高温度限制要求,为该包层方案的进一步结构优化和安全分析提供参考。 相似文献
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遥操作系统的设计是中国聚变工程实验堆(CFETR)中的一个关键问题,其中遥操作车的密封结构设计在整个停堆维护过程中起着重要作用,它是保证操作者可以安全、可靠和可重复性执行针对不同维护对象的维护任务的前提。文中首先介绍了CFETR遥操作转运车以及双密封门的设计,针对多层密封的特点进行了优化改进;然后对密封圈的选材做了分析,并详细计算了所需密封力的大小,根据结果选择硬度50HS的氟橡胶作为密封圈材料;最后设计了检漏的方案,对泄露情形做了分析,计算了压降和随时间变化关系,结果满足操作时间要求和系统安全要求。 相似文献
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The central post is one of the critical components for the low aspect ratio tokamak, which endures not only a tremendous ohmic heating because it carries a rather high current, but also a large neutron heating and irradiation owing to the plasma operation. The DS copper alloy Glidcop AL-25[8] was chosen as the conductor material for its adequate mechanical properties and physics properties. The central post has a cylindrical structure with lots of cooling channels. The length of the central post for the next generation of nuclear fusion spherical tokamaks will be more than 10 m or 20 m. The structural stability is very crucial. When the applied load is larger than the structure critical buckling load, the device will lose its stability and collapse. In order to calculate the critical buckling load, a 1/6-segment finite element model was used and the force acting on the central post was simulated. The results showed that the vertical compressive stresses mainly affect the stability of the central post. The linear buckling analysis results with finite element method based on small deformation theory were given in this paper. The relation curves and functions for buckling factor, depending on the different lengths and the radius of the central post, the diameter of cooling channel and the maximum allowable current density, were also shown. 相似文献
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ITER磁体过渡馈线的结构设计与优化 总被引:1,自引:0,他引:1
国际热核聚变实验堆ITER(Intemational Thermonuclear Experimental Reactor)是正在进行的一项大型国际合作项目.磁体过渡馈线是保证磁体正常工作的重要通道.本文对磁体过渡馈线系统各组件结构进行了设计,利用有限元软件对结构作了初步分析和结构优化.结果表明:现有结构完全满足设计要求;通过对现有结构进行优化,如增设横向筋板、L型加强板,简化超导电流传输线(Busbar)的弯曲结构等,可以达到降低成本、简化结构的目的. 相似文献
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The cryostat of HT-7U tokamak is a large vacuum vessel surrounding the entire basic machine with a cylindrical shell,a dished top and a flat bottom.The main function of HT-7U cryostat is to provide a thermal barrier between an ambient temperature test hall and a liquid helium-cooled superconducting magnet.The loads applied to the cryostat are from sources of vacuum pressure,dead weight,seismic events and electromagnetic forces originated by eddy currents.It also provides feed-through penetrations for all the conecting elements inside and outside the cryostat.The main material selected for the cryostat is stainless steel 304L.The structural analyses including buckling for the cryostat vessel under the plasma operation condition have been carried out by using a finite element code.Stress analysis results show that the maximum stress intensity was below the allowable value.In this paper,the structural analyses and design of HT-7U cryostat are emphasized. 相似文献