The blanket and divertor maintenance concept for ITER

Author

Toda, E. ; Ioki, K. ; Janeschitz, G. ; Maisonnier, D. ; Martin, E. ; Shibanuma, K. ; Kondoh, M. ; Burgess, T. ; Haange, R.

Author_Institution

JAERI, Ibaraki, Japan

Volume

1

fYear

1995

fDate

30 Sep-5 Oct 1995

Firstpage

399

Abstract

The Engineering Design of ITER has been conducted under an international joint effort aiming at realization of fusion energy. The remote maintenance of in-vessel components such as blanket and divertor is quite essential since personnel access to the core of ITER will be prohibited. The maintenance procedures and design concepts of the in-vessel remote handling system have been developed and the design feasibility has been validated through technology development. This paper describes the design outline developed for both blanket and divertor maintenance, the latest R&D status of the remote handling systems as well as the full-scale mock-up tests planned during the ITER EDA

Keywords

Tokamak devices; fusion reactor blankets; fusion reactor design; fusion reactors; nuclear reactor maintenance; ITER; blanket; divertor; full-scale mock-up tests; in-vessel remote handling system; maintenance; Cooling; Design engineering; Electronic design automation and methodology; Inductors; Personnel; Power engineering and energy; Rails; Remote handling; Research and development; System testing;

fLanguage

English

Publisher

ieee

Conference_Titel

Fusion Engineering, 1995. SOFE '95. Seeking a New Energy Era., 16th IEEE/NPSS Symposium

Conference_Location

Champaign, IL

Print_ISBN

0-7803-2969-4

Type

conf

DOI

10.1109/FUSION.1995.534251

Filename

534251