Thermal testing of TiC and TiN coating materials for tokamak limiters and walls.
スポンサーリンク
概要
- 論文の詳細を見る
Thermal testing of coating materials for tokamak limiters and walls was carried out by means of an electron beam equipment. The materials tested are TiC coated onto POCO graphite and TiC and TiN onto Mo by chemical vapor deposition. All the coating layers survived without exfoliation under 80% of the beam power which eroded the substrate material. This shows good thermal and mechanical contact between coatings and substrates. Allowable heat loads for upset conditions such as plasma disruption were estimated to be about 3.5 kW/cm<SUP>2</SUP> in uniform heating during 1 s for the three coating materials. The heat load limits in usual tokamak operation were also estimated in view of plasma contamination by limiter material evaporation. The limits in uniform heating for 1 s are about 3 kW/cm<SUP>2</SUP> for TiC on Mo, 2.5 kW/cm<SUP>2</SUP> for TiN on Mo, and 2 kW/cm<SUP>2</SUP> for TiC on POCO graphite. The TiC coating on Mo thus appears to be the most interesting choice within the framework of this study.
- 一般社団法人 日本原子力学会の論文
著者
-
Shibuki Kunio
Toshiba Tungaloy Co. Ltd.
-
KOIZUMI Hideo
Yokohama Metal Works, Toshiba Corp.
-
GOMAY Yoshio
Research & Development Center Toshiba Corp.
-
GOMAY Yoshio
Research & Development Center Toshiba Corp.
関連論文
- Lattice Continuity at Interface of Alumina-Coated Transition Metals
- Thermal testing of TiC and TiN coating materials for tokamak limiters and walls.
- Maintenance method for tokamak fusion reactors with downward access to torus inboard structures.
- Enhanced diffusion and compositional change in near surface layers of TiC under hydrogen ion bombardment.