Erlangen 2018 – wissenschaftliches Programm
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P: Fachverband Plasmaphysik
P 15: Helmholtz Graduate School IV - Plasma Wall Interaction
P 15.4: Vortrag
Mittwoch, 7. März 2018, 15:15–15:40, A 0.112
Radiation Damage Characterization in Tungsten — •Barbara Wielunska1,2, Matej Mayer1, Thomas Schwarz-Selinger1, Witold Zielinski3, Tomasz Plocinski3, Witold Chrominski3, and Lukasz Ciupinski3 — 1Max-Planck-Institut für Plasmaphysik Garching, Deutschland — 2Fakultät für Physik TUM, Garching, Deutschland — 3Wydzial Inzynierii Materialowej, Warszawa, Polska
Tungsten is a candidate material for the wall of future fusion reactors due to its low erosion yield and low hydrogen solubility. However, fusion neutron irradiation will induce radiation defects in the material. It is important to study the mechanism of defect creation and its influence on hydrogen retention in tungsten. Therefore tungsten samples were damaged with different ion species (p, D, He, Si, Fe, Cu, W) at energies between 0.3 and 20 MeV to different damage levels of 0.04 dpa and 0.5 dpa. For studying hydrogen retention in defects the samples were exposed to a low-temperature D plasma. The D depth distribution was obtained by nuclear reaction analysis using the D(3He, p)α reaction. Trapped D was measured by thermal desorption spectroscopy. Tungsten damaged by heavy ions (Si, Cu, Fe, W) to identical dpa values shows similar D depth profiles and D desorption spectra, i.e., the D retention is comparable. For tungsten damaged by light ions (p, D, He) the D retention shows larger differences. The damaged region was investigated by transmission electron microscopy. Differences in the dislocation structure in tungsten damaged by Si or W are visible although the D retention of those samples is almost identical.