Divertor

This requires establishing a separatrix-bounded magnetic configuration, typically achieved by creating poloidal field nulls (X-points) using external coils.

[1][2] It extracts heat and ash produced by the fusion reaction while protecting the main chamber from thermal loads, and reduces the level of plasma contamination due to sputtered impurities.

At present, it is expected that future fusion power plants will generate divertor heat loads greatly exceeding the engineering limits of the plasma-facing components.

[6] Despite some challenges, the island divertor concept has demonstrated great potential for managing power and particle exhaust in fusion reactors, and further research could lead to more efficient and reliable operation in the future.

This design permits adjustment of the stochastic layer size, situated between the confined plasma volume and the field lines ending on the divertor plate.