Progress in the Design of the Iter Divertor Maintenance System

E Martin,D Maisonnier,E Tada,J Blevins,T Burgess,G Cerdan,S Chiocchio,C Damiani, D Duglue,G Janeschitz,K Shibanuma,M Sironi,A Tesini,R Tivey

17TH IEEE/NPSS SYMPOSIUM ON FUSION ENGINEERING, VOLS 1 AND 2（1998）

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关键词

Tokamak devices,cryopumping,fusion reactor design,nuclear reactor maintenance,ITER,cryopumps,diagnostics,divertor,divertor RH ports,maintenance system,remote maintenance

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