Method for removing hydrogen detained on first wall in magnetic constraint device by ion involution oxygen plasma

A technology of oxygen plasma and plasma, which is applied in the field of vacuum technology and magnetic confinement fusion, can solve the problems of reduced life of magnets, achieve the effects of reducing hydrogen retention, reducing particle recirculation, and reducing safety and environmental problems

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

[0006] EAST is a fully superconducting tokamak device. Repeated excitation / demagnetization of superconductors will reduce the life of the magnet, and it needs to meet the removal of hydrogen isotopes in the plasma discharge interval, so hydrogen needs to be carried out under the condition of maintaining a strong longitudinal magnetic field. isotope removal

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  • Method for removing hydrogen detained on first wall in magnetic constraint device by ion involution oxygen plasma

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[0018] The method for ion cyclotron oxygen plasma to remove hydrogen retention in the first wall of the magnetic confinement device, firstly use the plasma-assisted chemical removal method, and keep the longitudinal magnetic field at 1.5-2.0T, first bake the first wall temperature to 400~ 470K, fill the vacuum chamber with oxygen or a certain proportion of helium and oxygen mixed gas, use pulsed ion cyclotron wave injection to excite oxygen plasma discharge, and realize the removal of the first wall hydrocarbon redeposited layer, thereby effectively removing the residue remaining in the device. Hydrogen retention on one wall. The ion cyclotron antenna is used in the nuclear fusion experimental device. The ion cyclotron wave power during the treatment of the first wall is 10-40kW, the frequency is 30MHZ, and the oxygen plasma pressure is 0.01-0.1Pa. A one second on and one second off pulsed ion cyclotron wave injection excites the oxygen plasma. The ions in the oxygen plasma w...

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Abstract

The invention discloses a method for removing hydrogen detained on a first wall in a magnetic constraint device by ion involution oxygen plasma. According to carbon and hydrogen codeposition characteristic in the magnetic constraint 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, under condition of keeping longitudinal magnetic fields of 1.5-2.0T and wall temperature of 400-470K, a ion involution plasma technology is employed, oxygen which is easy to react with carbon and hydrogen is employed to form ion involution 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 technology is a unique and effective technology, 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. Simultaneously, the treatment for the first wall can be carried out under condition that longitudinal field coil is not demagnetized, and is more suitable for future international thermonuclear fusion experiment reactor ITER and future fusion reactor.

Description

technical field [0001] The invention relates to the fields of vacuum technology and magnetic confinement fusion, in particular to a method for removing hydrogen retention on the first wall of a magnetic confinement device by ion cyclotron oxygen plasma. 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 EAST and future fusion reactor...

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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 胡建生李建刚赵燕平王小明
Owner INST OF PLASMA PHYSICS CHINESE ACAD OF SCI
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