Erschienen:
[Erscheinungsort nicht ermittelbar]: [Verlag nicht ermittelbar], 2020
Sprache:
Englisch
Identifikator:
Entstehung:
Hochschulschrift:
Dissertation, 2020
Anmerkungen:
Beschreibung:
Tungsten (W) is the main candidate material for divertor component and plasma-facing components (PFCs) armor in the nuclear fusion reactor. In the magnetic confinement reactor called Tokamak", the confined hot plasma is directed by the magnetic field to the divertor component in order to remove the impurities and He ash. Moreover, the surrounding components in the reactor vacuum chamber are irradiated by the fast neutron generated from D-T reaction. These high heat flux and neutron flux will degrade the mechanical performance of the divertor component. Therefore, the investigation of mechanical properties after high-temperature neutron irradiation is essential for designing a divertor that can endure this harsh environment. Twelve different W grades were investigated to explore the effect of initial microstructure, presence of strengthening particles, fabrication route applied, potential of additive manufacturing to deliver the materials with sufficient resistance to the neutron irradiation. In order to reach these targets, the studies have been performed across three directions: (i) miniaturized mechanical testing methods were developed, adapted, or modified in terms of specimen design, loading condition, loading fixtures, and data reduction schemes