A.A. Haasz

TL;DR: In this article, the authors review the underlying physical processes and the existing experimental database of plasma-material interactions both in tokamaks and laboratory simulation facilities for conditions of direct relevance to next-step fusion reactors.

TL;DR: In this article, the authors present the results of current predictions both in terms of implantation and codeposition rates, and critically discuss their uncertainties and sensitivity to important design and operation parameters such as the plasma edge conditions, the surface temperature, the presence of mixed-materials, etc.

TL;DR: In this article, the authors used SIMS measurements of implantation profiles and using the multi-trap diffusion code TMAP7 to model the thermal desorption profiles of single crystal tungsten.

TL;DR: The results of the Coordinated Research Project (CRP) on the overall topic of tritium inventory in fusion reactors during the period 2001-2006 are summarized in this paper together with recommendations for ITER as discussed by the authors.

TL;DR: In this paper, the effect of ion-induced damage due to prior ion implantation on deuterium retention in tungsten has been investigated, and it was shown that 1.5 keV D 3 + ions (500 eV/D + ) to 10 23 D/m 2 at 500 K showed a 3-4 increase in retention for specimens previously exposed to a fluence of 10 24 D/M 2 and a factor of 6-7 increase for specimens recently exposed to 3-times-10 24 Dm 2 over specimens exposed only to an incident flu