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Implantation, flux and recoil distributions for plasma species impinging on tokamak divertor materials

  • Author(s): Moshman, Nathan David
  • et al.
Abstract

A time-dependent one-dimensional continuum transport code, WALL-PSI, is being developed by author's thesis commitee to be a physics component of the integrated core-edge-wall project. WALL-PSI calculates wall temperature, concentrations of trapped plasma species and other quantities needed to couple tokamak edge plasma to coolant facing components (CFCs). One purpose of developing this code is to help estimate suitability and longevity of divertor plate materials for ITER. For every possible edge plasma species impinging on every potential wall target material combination there will be a unique implanted particle density distribution (\[phi\]impl), recoil density distribution (\[phi\]recoil) and scalar flux distribution (Jscal) that will change with incident energy and angle. The reflection coefficient (RN), energy reflection coefficient (Re), average projectile range and sputtering yield \[gamma\] are also needed for integration into WALL-PSI. A binary collision code, TRIDYN, is used to generate the data over an energy range from 0.1eV to 5000eV and normal to near tangential incidence. Numeric routines are written to run many cases automatically, synthesize and analyze the data. In some cases analytic functions are fit to the data and various trends are reported. C-functions are written which take, as input: projectile and target species, energy and angle of incidence and depth and return estimations of local implanted particle density, local implanted recoil density, local particle flux, reflection coefficient, energy reflection coefficient and sputtering yield. Trends in data are reported and C-functions are used in WALL-PSI.

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