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介绍使用在超高超人空下,被抽气体主要为CO的小体积、大抽速、多发源钛升华泵的设计思想、结构特点和部分测试结果。 相似文献
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EAST超导托卡马克是具有非圆截面的核聚变试验装置,其真空室内部部件在等离子体热壁运行时将承受相当大的热应力和电磁载荷,在某些工况下的应力可能超出材料的强度极限.对EAST超导托卡马克装置中的真空室内部部件的应力状况进行了计算分析,从理论上提出了运用润滑材料的必要性;研制了一种金属基多层固体自润滑复合材料,摩擦学性能测试表明,该自润滑复合材料具有特殊的梯度结构,能保证高的机械强度,且具有优异的摩擦磨损性能和连续润滑功能;有限元计算和模拟件的加热变形试验表明,该自润滑复合材料真空中的滑动摩擦因数不超过0.15,能减少内部部件应力集中的情况,避免应力过大对热沉材料造成的破坏,保障超导托卡马克装置聚变试验的安全. 相似文献
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Modal analysis and seismic response analysis were carried out for the equatorial diagnostic port plug of international thermonuclear
experimental reactor (ITER). The aim of the theoretical analysis is to verify structural strength and reliability of the device.
The working condition includes one-dimensional seismic wave and two-dimensional seismic wave. Modal analysis of the device
shows that primary vibration is inclined to occur in low-order modes. The horizontal (X-direction, Y-direction) maximum vibration appears at the first and the fourth eigen modes, with the natural frequency of 70.59 and 215.88
Hz respectively, and the vertical (Z-direction) primary vibration appears at the second eigen mode with the natural frequency of 82.85 Hz. According to the results
of the finite element analysis (FEA) program, the weak portions of the device are distributed in the joint of port body with
blanket shielding module (BSM) and inner side wall of ribbed plate for lifting flange, the maximum von Mises stress is 14.8
MPa with the Y-direction seismic wave. In accordance with the design criteria, the destructive effect is far below the failure boundary,
and the structural reliability of the equatorial diagnostic port plug can meet the requirements of the design specifications.
Foundation item: Project(10405024) supported by the National Natural Science Foundation of China; Project supported by International Thermonuclear
Experimental Reactor Organization in France 相似文献
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HT-7U真空室支撑结构的数值模拟与实验研究 总被引:2,自引:1,他引:2
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。 相似文献
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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. 相似文献
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An orthogonal experimental scheme was designed for optimizing a water-cooled structure of the divertor plate.There were three influencing factors:the radius R of the watercooled pipe,and the pipe spacing L1 and L3.The influence rule of different factors on the cooling effect and thermal stress of the plate were studied,for which the influence rank was respectively R>L1>L3 and L3>R>L1.The highest temperature value decreased when R and L1increased,and the maximum thermal stress value dropped when R,L1 and L3 increased.The final optimized results can be summarized as:R equals 6 mm or 7 mm,L1 equals 19 mm,and L3 equals 20 mm.Compared with the initial design,the highest temperature value had a small decline,and the maximum thermal stress value dropped by 19%to 24%.So it was not ideal to improve the cooling effect by optimizing the geometry sizes of the water-cooled structure,even worse than increasing the flow speed,but it was very effective for dropping the maximum thermal stress value.The orthogonal experimental method reduces the number of experiments by 80%,and thus it is feasible and effective to optimize the water-cooled structure of the divertor plate with the orthogonal theory. 相似文献
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The Chinese Fusion Engineering Test Reactor (CFETR) represents the next generation of full superconducting fusion reactors in China.Recently,CFETR was redesigned with a larger size and will be operated in two phases.To reduce the heat flux on the target plate,a snowflake (SF) divertor configuration is proposed.In this paper we show that by adding two dedicated poloidal field (PF) coils,the SF configuration can be achieved in both phases.The equilibria were calculated by TEQ code for a range of self-inductances li3.The coil currents were calculated at some fiducial points in the flattop phase.The results indicate that the PF coil system has the ability to maintain a long flattop phase in 7.5 and 10 MA inductive scenarios for the single null divertor (SND) and SF divertor configurations.The properties of the SF configuration were also analyzed.The connection length and flux expansion of the SF divertor were both increased significantly over the SND. 相似文献
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