Tokamak hybrid divertor magnetic field configuration construction method
A tokamak and construction method technology, applied in nuclear reactors, nuclear power generation, climate sustainability, etc., can solve the problems of increasing the plasma wetting area, dispersion, high thermal load of the divertor, etc., and achieve the expansion of the magnetic surface of the large target plate coefficient, enhanced wetted area, enhanced connection length effect
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[0025] A method for constructing a magnetic field configuration of a tokamak hybrid divertor according to the present invention will be described in detail below with reference to the drawings and embodiments.
[0026] The configuration of the hybrid divertor is mainly combined with the structural characteristics of the tokamak magnetic confinement fusion reactor device, that is, the space on the side of the strong field is compact and the space on the side of the weak field is relatively abundant. The side of the scrape-off layer near the divertor target plate produces the plasma equilibrium configuration of the second X point, and by optimizing the distance between the second X point and the first X point, etc., a divertor configuration with snowflake subtraction (left) is formed , enhance the plasma wetted area and connection length of the inner target plate, and achieve the goal of reducing the thermal load of the inner divertor target plate and improving particle control u...
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