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

Volume

1

fYear

1997

fDate

6-10 Oct 1997

Firstpage

331

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;

fLanguage

English

Publisher

ieee

Conference_Titel

Fusion Engineering, 1997. 17th IEEE/NPSS Symposium

Conference_Location

San Diego, CA

Print_ISBN

0-7803-4226-7

Type

conf

DOI

10.1109/FUSION.1997.687049

Filename

687049