The Plasma Boundary of Magnetic Fusion Devices
By P. Ghendrih. 2001
371 citations recorded by the source corpus.
Subfields: Biomedical Engineering, Materials Chemistry, Nuclear and High Energy Physics
View Paper: https://www.semanticscholar.org/paper/fd4ce3b5d0137af2ff2d2940e98d0eba115de924
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In Biomedical Engineering
In Materials Chemistry
In Nuclear and High Energy Physics
Citations in the corpus
- A new experimental classification of divertor detachment in ASDEX Upgrade (2013, background): “According to the TPM the ion flux reaching the divertor target is proportional to the square of the upstream separatrix density nsep (equation (5)).”
- 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.”
- Impurity seeding for tokamak power exhaust: from present devices via ITER to DEMO (2013, methodology): “For time-independent conditions, a 2-point model for a flux bundle which connects midplane and target can be used to obtain a reasonable description of plasma parameters with a self-consistent treatment of radiative losses [21] [22] [23] [24].”
- Basic physical processes and reduced models for plasma detachment (2018, neutral): “Equations (15c)–(17c) are identical to those in [15], equations (5.”