Abstract
High ductile-to-brittle transition temperature, recrystallization-induced embrittlement, and neutron-irradiation-induced embrittlement are potential drawbacks related to the mechanical properties of tungsten (W) for plasma facing materials of fusion reactor divertors. To improve the mechanical properties, resistance to recrystallization and neutron irradiation, W materials modified by potassium doping and alloying by rhenium have been developed. In this paper, thermal shock behaviors of these W materials under high heat flux tests were investigated, which simulated an edge localized mode of plasma occurring in fusion reactors as a transient event. The thermal shock tests were performed with an electron beam facility, JUDITH 1, and post-mortem analyses to evaluate the damage caused by the thermal shock tests were carried out.
Original language | English |
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Article number | 014020 |
Journal | Physica Scripta |
Volume | 2020 |
Issue number | T171 |
DOIs | |
Publication status | Published - 2020 Jan 1 |
Event | 17th International Conference on Plasma-Facing Materials and Components for Fusion Applications, PFMC 2019 - Eindhoven, Netherlands Duration: 2019 May 20 → 2019 May 24 |
Keywords
- Crack formation
- Potassium doping
- Rhenium addition
- Thermal shock
- Tungsten
ASJC Scopus subject areas
- Atomic and Molecular Physics, and Optics
- Mathematical Physics
- Condensed Matter Physics