Abstract
Coupled fluid plasma and kinetic Monte Carlo neutrals simulations in a linear configuration are reported. The configuration mimics the tokamak divertor plasma channel contacting a target surface with nearby wall. We calculate the parameters of the source plasmas, 3-5 m from the target, required to produce high recycling target plasmas recently simulated for ITER. It is shown that the source plasma needs to deliver heat fluxes of 10-20 MW/m2, ion fluxes of 1023/m2/s, densities of 2-6 × 10 19/m3, and electron and ion temperatures of 15-30 eV over a plasma radius of 5-6 cm. The neutral H and H2 fluxes to the vessel wall are calculated to be comparable to those measured in the divertor regions of today's tokamaks. These results identify some design features for a prospective plasma material test station and the research required for this plasma source.
| Original language | English |
|---|---|
| Pages (from-to) | S925-S929 |
| Journal | Journal of Nuclear Materials |
| Volume | 438 |
| Issue number | SUPPL |
| DOIs | |
| State | Published - 2013 |
Funding
Work supported in part by the U.S. DOE under Contract DE-AC05-00OR22725.