Thermal shock behavior of potassium doped and rhenium added tungsten alloys

S. Nogami, G. Pintsuk, K. Matsui, S. Watanabe, M. Wirtz, T. Loewenhoff, Akira Hasegawa

研究成果: Conference article査読

5 被引用数 (Scopus)

抄録

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.

本文言語English
論文番号014020
ジャーナルPhysica Scripta
2020
T171
DOI
出版ステータスPublished - 2020 1月 1
イベント17th International Conference on Plasma-Facing Materials and Components for Fusion Applications, PFMC 2019 - Eindhoven, Netherlands
継続期間: 2019 5月 202019 5月 24

ASJC Scopus subject areas

  • 原子分子物理学および光学
  • 数理物理学
  • 凝縮系物理学
  • 物理学および天文学(全般)

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