DocumentCode
3594194
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
Volume
1
fYear
1997
Firstpage
373
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;
fLanguage
English
Publisher
ieee
Conference_Titel
Fusion Engineering, 1997. 17th IEEE/NPSS Symposium
Print_ISBN
0-7803-4226-7
Type
conf
DOI
10.1109/FUSION.1997.687058
Filename
687058
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