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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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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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