Thermonuclear fusion reactor superconducting coil heat shielding component and preparation method thereof

A technology of thermonuclear fusion reactors and superconducting coils, applied in the field of thermonuclear fusion reactors, can solve problems such as low vacuum sealing performance, low connection quality, and degradation of mechanical properties, so as to improve production efficiency, improve heat conduction efficiency, and benefit The effect of quality control

Pending Publication Date: 2021-01-22
SOUTHWESTERN INST OF PHYSICS
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  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

[0008] The purpose of the present invention is to design a thermonuclear fusion reactor superconducting coil thermal shielding part and its preparation method, which is used to solve the problems of poor connection quality, degradation of mechanical properties and vacuum sealing performance of the superconducting coil thermal shielding part in the prior art. low technical issues

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  • Thermonuclear fusion reactor superconducting coil heat shielding component and preparation method thereof
  • Thermonuclear fusion reactor superconducting coil heat shielding component and preparation method thereof

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Embodiment Construction

[0041] Below in conjunction with accompanying drawing and embodiment the present invention is further introduced:

[0042] A thermonuclear fusion reactor superconducting coil heat shielding component, comprising: F-type tube A1, F-type tube B2, copper plate A3, copper plate B4, copper plate C5, copper chromium zirconium steel pipe brazing assembly 6; the copper plate A3 and copper plate B4 The copper chromium zirconium steel pipe brazing assembly 6 is connected between them, and the copper chromium zirconium steel pipe brazing assembly 6 is arranged between the copper plate B4 and the copper plate C5; the two ends of the copper chromium zirconium steel pipe brazing assembly A6 are respectively provided with F Type Tube A1 and Type F Tube B2.

[0043] The copper chromium zirconium steel pipe brazing assembly 6 includes: copper chromium zirconium block 10, brazing material 7, filler tank 8 and steel pipe 9;

[0044] The copper-chromium-zirconium block 10 has a strip-shaped "con...

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Abstract

The invention belongs to the technical field of thermonuclear fusion reactors, and particularly relates to a thermonuclear fusion reactor superconducting coil heat shielding component and a preparation method thereof. The thermonuclear fusion reactor superconducting coil heat shielding component comprises an F-shaped pipe A, an F-shaped pipe B, a copper plate A, a copper plate B, a copper plate Cand copper-chromium-zirconium steel pipe brazing assemblies, wherein the copper plate A3 and the copper plate B4 are connected through the copper-chromium-zirconium steel pipe brazing assembly, the copper-chromium-zirconium steel pipe brazing assembly is arranged between the copper plate B and the copper plate C, and the F-shaped pipe A and the F-shaped pipe B are arranged at the two ends of the copper-chromium-zirconium steel pipe brazing assembly correspondingly.

Description

technical field [0001] The invention belongs to the technical field of thermonuclear fusion reactors, and in particular relates to a thermonuclear fusion reactor superconducting coil thermal shielding part and a preparation method thereof. Background technique [0002] ITER is currently the largest superconducting tokamak device in the world. In the ITER facility, the magnetic confinement of the plasma is achieved by means of different superconducting coils. The fusion reactor magnet system includes 18 correction coils. These superconducting coils must be kept below extremely low temperatures to maintain superconductivity and maintain the stable operation of the ITER device. However, each poloidal field coil box in contact with the correction field coil generates about 16.596kW of heat under the magnetic field, in order to ensure the normal operation of the correction field superconducting magnet during the operation of the fusion reactor. The thermal shielding part connec...

Claims

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Application Information

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IPC IPC(8): H01F6/04H01F41/04G21B1/05G21B1/11
CPCH01F6/04H01F41/048G21B1/057G21B1/11Y02E30/10
Inventor 许丹李鹏远张腾孙振超柳根魏海鸿罗蓉蓉李敏
Owner SOUTHWESTERN INST OF PHYSICS
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