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Hannover 2020 – wissenschaftliches Programm

Die DPG-Frühjahrstagung in Hannover musste abgesagt werden! Lesen Sie mehr ...

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P: Fachverband Plasmaphysik

P 16: Poster Session 3

P 16.7: Poster

Mittwoch, 11. März 2020, 16:30–18:30, Empore Lichthof

The GIRAFFE experiment: in situ tensile tests of irradiated tungsten fibers — •Bailey Curzadd1,2, Johann Riesch1, Till Höschen1, Alexander Feichtmayer1,2, and Rudolf Neu1,21Max-Planck-Institut für Plasmaphysik, Garching, Deutschland — 2Technische Universität München, München, Deutschland

Although its low erosion rate and low retention of tritium make tungsten (W) the preferred plasma-facing material for future fusion reactors, its low-temperature brittleness is a potentially critical vulnerability that could lead to the premature failure of plasma-facing components. The degradation of essential material properties by the fusion environment - especially by neutron irradiation and gas atoms (H/He) trapped in the microstructure - greatly increases the likelihood of component failure. However, the degradation of W in the fusion environment is poorly characterized. For this reason, a novel experiment to better understand the mechanisms by which the mechanical properties of W are worsened by radiation damage and trapped impurities is in development. A principal research goal is the investigation of synergistic interactions between the factors that lead to material deterioration. Displacement damage will be produced by bombardment of samples with protons or heavy ions. Samples will be subsequently or simultaneously loaded with impurity gases, and the mechanical properties determined via in situ tensile testing. Due to the low penetration depth of protons and heavy ions in W, thin fibers and foils (≈ 5 µm) are foreseen as samples. The fine microstructure of these samples enables the simulation of bulk material behavior.

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