Title :
Status of the engineering design of the ITER divertor
Author :
Chiocchio, S. ; Antipenkov, A. ; Federici, G. ; Ibbott, C. ; Heidl, H. ; Jakeman, R. ; Janeschitz, G. ; Martin, E. ; Raffray, R. ; Tivey, R.
Author_Institution :
Max-Planck-Inst. fur Plasmaphys., Garching bei Munchen, Germany
Abstract :
In this paper we present the main features of the ITER divertor final design from an engineering point of view and describe the present choices regarding layout, geometry and material selection. The assessment of the detailed design shows that the divertor is able to withstand the thermal and electromagnetic loading conditions foreseen for ITER, and that the estimated lifetime of the plasma facing components, in relation to the thermal low cycle fatigue of the heat sink, or to the expected armour erosion, meets the ITER requirements
Keywords :
Tokamak devices; fusion reactor design; fusion reactor materials; ITER divertor; armour erosion; electromagnetic loading; engineering design; final design; geometry; heat sink; layout; material selection; plasma facing components; thermal loading; thermal low cycle fatigue; Design engineering; Geometry; Helium; Impurities; Physics; Plasma confinement; Plasma density; Plasma materials processing; Plasma temperature; Thermal loading;
Conference_Titel :
Fusion Engineering, 1997. 17th IEEE/NPSS Symposium
Conference_Location :
San Diego, CA
Print_ISBN :
0-7803-4226-7
DOI :
10.1109/FUSION.1997.687049
