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Method for removing hydrogen detained on first wall in nuclear fusion device by direct current glow oxygen plasma

An oxygen plasma, DC glow technology, applied in the field of vacuum technology and magnetic confinement fusion, which can solve problems such as inability to remove hydrogen isotopes

Inactive Publication Date: 2009-09-16
INST OF PLASMA PHYSICS CHINESE ACAD OF SCI
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Problems solved by technology

And the depth of these conventional discharge cleaning is limited by the energy of the ions, which can only clean the depth of a few nanometers, and cannot remove the hydrogen isotopes trapped in the redeposition layer tens of microns thick

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  • Method for removing hydrogen detained on first wall in nuclear fusion device by direct current glow oxygen plasma

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Embodiment Construction

[0021] First, use the nuclear fusion experimental device HT-7 internal baking system to bake the first wall to 400-470K, and fill the vacuum chamber with pure oxygen, or a mixed gas of helium and oxygen, such as 10% oxygen and 90% helium, The inflation pressure is 10-20Pa.

[0022] The DC glow discharge is used in the nuclear fusion experimental device, with the vacuum chamber as the negative pole, 2-4 electrodes extending into the vacuum chamber as the positive pole, and the voltage applied between the two poles is 1-2 kV to break down the gas and Generate a stable DC glow plasma discharge, adjust the glow discharge current to 2-4A for each electrode, and stabilize the voltage at 200-300V and the air pressure at 0.5-10Pa. The ions in the oxygen plasma will effectively bombard and interact with the first wall of the vacuum chamber. After 1-10 hours of discharge cleaning, the redeposition layer on the first wall will be removed, and at the same time, the redeposition layer will...

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Abstract

The invention discloses a method for removing hydrogen detained on a first wall in a nuclear fusion device by direct current glow oxygen plasma, which is mainly used for creating optimized wall condition for effective operation of nuclear fusion device plasma physical experiment economy and reducing safely and environment problems due to radioactive tritium detained on the first wall of future device. The inventin is characterized in that according to carbon and hydrogen codeposition characteristic in the device, a plasma auxiliary chemical removing method is used, on a HT-7 superconducting tokmak and a EAST device having similar bit-type with ITER, and first wall temperature of 400-470K, a direct current glow plasma technology is employed, oxygen which is easy to react with carbon and hydrogen is employed to form radio frequency oxygen plasma for removing carbon hydrogen re-deposition layer on the first wall, thereby effectively removing hydrogen detained on the first wall of a device. The invention creates excellent wall condition for re-deposition layer removal on the first wall, reduction of hydrogen detained in the device, particle recirculation lowering and nuclear fusion device high efficiency operation, and reduces safely and environment problems of future nuclear fusion device due to radioactive tritium detained on the first wall.

Description

technical field [0001] The invention relates to the fields of vacuum technology and magnetic confinement fusion; in particular, it relates to a wall treatment method for removing hydrogen retention on the first wall by direct current glow oxygen plasma in a nuclear fusion device. Background technique [0002] Impurity suppression is an important issue in tokamak operation. The current tokamak needs to limit the impurities in the plasma through the first wall tempering to obtain high-quality plasma. In the upcoming all-superconducting tokamak devices with quasi-steady-state high-parameter plasma operation, such as EAST and ITER, in addition to completing impurity confinement, it is also necessary to solve the retention of hydrogen isotopes in the vacuum chamber. The research on the removal technology and mechanism of a-C:H(D,T) deposition layer in the tokamak fusion experimental device can provide scientific understanding for the construction, operation and experiment of EAS...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21B1/25G21B1/13H05H1/24
CPCY02E30/128Y02E30/10
Inventor 胡建生李建刚王小明
Owner INST OF PLASMA PHYSICS CHINESE ACAD OF SCI
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