Graphites as plasma facing material of a large fusion device
Abstract
Several graphites, such as the first wall materials of the Large Helical System, are evaluated in terms of erosion, thermal shock resistance, and recycling. Adequate graphites are suggested, and the required conditions such as baking, cooling, and the discharge cleaning are discussed.
- Publication:
-
Plasma Physics and Controlled Nuclear Fusion: Next Generation Experiments in Helical Systems
- Pub Date:
- March 1990
- Bibcode:
- 1990ppcn.conf...57H
- Keywords:
-
- Erosion;
- Fusion Reactors;
- Graphite;
- Heliotrons;
- Plasmas (Physics);
- Shock Resistance;
- Walls;
- Baking;
- Cleaning;
- Cooling;
- Corrosion Resistance;
- Recycling;
- Thermal Shock;
- Plasma Physics