The Plasma Boundary of Magnetic Fusion Devices

By P. Stangeby. 2000

1,922 citations recorded by the source corpus.

Subfields: Nuclear and High Energy Physics

View Paper: https://www.semanticscholar.org/paper/c313c7b673a06641fdb0ba076062a06869954a49

How researchers see this paper

The researchers whose trusted networks rank it highest, strongest advocate first. Every researcher gets a different order.

In Nuclear and High Energy Physics

Citations in the corpus

Surface heat loads on the ITER divertor vertical targets (2017, background): “22 of [21]? In a study of microscopic erosion patterns on a tokamak limiter, a comparison of ion impact angles calculated with and without the sheath electric field [18] suggests that there is a modest steepening of the ion impact angle of around a mere 1°.”
The JOREK non-linear extended MHD code and applications to large-scale instabilities and their control in magnetically confined fusion plasmas (2020, methodology): “, in the divertor region or for grids extended to the true physical wall) sheath boundary conditions are applied as commonly done in divertor physics codes [63].”
On heat loading, novel divertors, and fusion reactors (2006, methodology): “is the ratio of these forces, where the values of the coefficients can be found in references [27, 39].”
Overview of the physics and engineering design of NSTX upgrade (2011, background): “Recent dedicated multi-machine studies in the US [163–165] have explored the λq scaling further and find a strong inverse dependence on plasma current but a weak dependence on magnetic field and power into the SOL.”
Physics of ultimate detachment of a tokamak divertor plasma (2017, background): “The plasma–neutral ‘friction’ per se, which in some publications (e.g. Stangeby 1993; Stangeby 2000) is believed to be responsible for the reduction of Γw, actually cannot change the plasma flux.”
Effects of divertor geometry on tokamak plasmas (2001, background): “The physical basis for this strong influence is twofold: • For typical parameters at the plasma edge, the ionization mean free path of neutrals recycled at the divertor target is similar (usually shorter) to the typical dimensions of the divertor plasma (Stangeby 2000).”