Title :
Thermal cycling of water-cooled divertor mock-ups
Author :
Linke, J. ; Duwe, R. ; R?¶dig, M. ; Schuster, A.
Author_Institution :
Forschungszentrum Julich GmbH, Germany
Abstract :
During normal operation, the high heat flux components of ITER will suffer cyclic heat loads in the order of more than 5 MW/m2 . Candidate armor materials are carbon materials, tungsten alloys and beryllium. Most likely copper alloys will be used for the heat sink. In order to study the performance of several joining techniques between these materials, simulation experiments were performed in an electron beam facility. This paper describes the performance of beryllium-copper joints
Keywords :
Tokamak devices; fusion reactor design; Be; Be-C joints; C; ITER; armor materials; beryllium; carbon materials; cyclic heat loads; electron beam facility; heat sink; high heat flux components; joining techniques; normal operation; thermal cycling; tungsten alloys; water-cooled divertor mock-ups; Cooling; Copper alloys; Electron beams; Frequency; Heat sinks; Heating; Organic materials; Temperature; Testing; Tungsten;
Conference_Titel :
Fusion Engineering, 1997. 17th IEEE/NPSS Symposium
Print_ISBN :
0-7803-4226-7
DOI :
10.1109/FUSION.1997.687058
