Development of plasma facing components for ITER at Efremov Institute

Author

Belyakov, V.A. ; Filatov, O.G. ; Mazu, I.V.

Author_Institution

Efremov (D.V.) Sci. Res. Inst. of Electrophys. Apparatus, St. Petersburg, Russia

Volume

1

fYear

1997

fDate

6-10 Oct 1997

Firstpage

393

Abstract

Review of the design and R&D activity related to ITER divertor components development performed in Russia during recent years is presented. The scope of the design work and the codes used in this analysis are briefly reviewed. Among a variety of R&D works the key issues are presented: selection and study of armour materials, development of joining technology and mock-ups manufacturing, high heat flux tests of materials and components. The experimental and technological facilities used for this work are reviewed and a number of the alternative design solutions and experimental approaches are briefly discussed as well

Keywords

Tokamak devices; fusion reactor design; fusion reactor materials; joining processes; Efremov Institute; ITER; Russia; armour materials; divertor components; fusion reactor design; high heat flux tests; joining technology; mockups manufacturing; plasma facing components; technological facilities; Joining materials; Manufacturing; Materials testing; Plasma materials processing; Research and development; Superconducting materials; Thermal conductivity; Thermal resistance; Thermal stresses; Tokamaks;

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.1997.687063

Filename

687063