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P: Fachverband Plasmaphysik
P 19: Poster II
P 19.28: Poster
Thursday, March 31, 2022, 16:00–17:30, P
Investigation of synergistic effects of irradiation damage, hydrogen retention and mechanical loading on tungsten — •Alexander Feichtmayer1,2, Bailey Curzadd1,2, Sebastian Estermann1,2, Maximilian Fuhr1,2, Till Höschen1, Robert Lürbke1,3, Johann Riesch1, Thomas Schwarz-Selinger1, Dominik Viebke1,2, and Rudolf Neu1,2 — 1Max-Planck-Institut für Plasmaphysik, 85741 Garching, Germany — 2Technische Universität München, 85741 Garching, Germany — 3RWTH Aachen University, 52062 Aachen, Germany
One of the major challenges in the realization of a nuclear fusion power plant such as DEMO is the development of suitable materials for the highly loaded plasma-facing components. The main candidate for the armor inside a future fusion reactor is tungsten. It has a high melting point, low erosion rate and low hydrogen retention, but it is brittle below 500-600 K and irradiation causes further embrittlement.
Since there is no sufficient source for 14.1 MeV fusion neutrons for material tests available, it is proposed to simulate the damage by means of ion irradiation. To investigate the synergistic effects, in-situ experiments such as stress relaxation and tensile tests are performed on thin tungsten wires, during irradiation with high-energy ions and simultaneous loading with low-energy hydrogen. An additional sample heater will allow irradiation and testing under fusion-relevant temperatures up to 1800 K. Due to the fine grain structure of the samples, the experiments will provide results that can be transferred to bulk tungsten and serve also for the development of tungsten fiber-reinforced composites.