T. Kenmotsu (Sp), KIBI International University, Takahashi (Japan); T. Ono, Okayama University of Science (Japan); T. Kawamura, Chubu University, Kasugai (Japan)
The hydrogen retention and recycling properties of first wall materials during and after the bombardment with hydrogen from the plasma are important factors controlling the particle balance and the isotope composition of the plasma, as well as the tritium inventory of the vessel walls. Deuterium retention and release from a surface during implantation on several plasma-facing materials have been studied extensively. García-Rosales et al. have measured on re-emission and thermal and isothermal desorption of deuterium from a tungsten material in ASDEX-upgrade at low-energy bombardment (100eV) and experimental data are compared with model calculations with the PIDAT code [1].
In this work, we tried to follow García-Rosales’s experimental data on fluxes of re-emission and desorption of deuterium from a tungsten material using the ACAT-DIFFUSE code [2]. The retention and the depth distribution of deuterium in a tungsten material have been also calculated with ACAT-DIFFUSE. The radiation-enhanced diffusion of deuterium and the damage effect of the trap energy are taken into account. Simulation results calculated with ACAT-DIFUSE are compared with experimental data.
References
[1] C. García-Rosales et al., J. Nucl. Maer. 233-237 (1996) 803
[2] Y. Yamamura, Nucl. Instr. Meth. B28 (1987) 17
