SMuK 2021 – wissenschaftliches Programm
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P: Fachverband Plasmaphysik
P 2: Magnetic Confinement, Plasma-Wall Interaction & Helmholtz Graduate School I
P 2.2: Vortrag
Montag, 30. August 2021, 11:30–11:55, H6
In situ mechanical characterization of ion-irradiated tungsten — •Bailey Curzadd1,2, Max Boleininger3, Maximilian Fuhr1,2, Till Höschen1, Robert Lürbke1,4, Johann Riesch1, and Rudolf Neu1,2 — 1Max-Planck-Institut für Plasmaphysik, Garching, Germany — 2Technical University Munich, Garching, Germany — 3CCFE, UKAEA, Abingdon, UK — 4RWTH Aachen, Aachen, Germany
Although its low erosion and low retention of tritium make tungsten (W) the preferred plasma-facing material for future fusion reactors, its low-temperature brittleness is a critical vulnerability that could lead to the premature failure of plasma-facing components. Additionally, the degradation of essential material properties in the reactor environment – especially by neutron radiation and H/He trapped in the microstructure – greatly increases the likelihood of component failure, yet the degradation of W in a fusion environment is poorly characterized. For this reason, a novel in situ accelerator experiment was developed to characterize the mechanisms by which the mechanical properties of W are altered by radiation damage and trapped impurities, with a principle focus on the investigation of synergistic interactions between the factors that lead to material deterioration. This experiment uses thin drawn W wires prepared to a diameter of 5 *m to enable complete irradiation of the sample cross-section and allows simultaneous damaging and implantation of impurity atoms. The capabilities of the system and the results of the first experimental campaign examining radiation-induced relaxation of tensile stress in W will be presented.