Alcator C-Mod inner divertor upgrade design and analysis

Author

Titus, Peter H. ; Zaks, J. ; DeMaria, M. ; LaBombard, B. ; Granetz, R. ; Irby, J. ; Lipshultz, B. ; Fitzgerald, E. ; Childs, R. ; Beck, W. ; Marmar, E. ; Gwinn, D. ; Hutchinson, I. ; Boivin, R. ; Burke, W.

Author_Institution

Plasma Sci. & Fusion Center, MIT, Cambridge, MA, USA

fYear

2002

fDate

2002

Firstpage

333

Lastpage

336

Abstract

In 1993 there were indications that the C-Mod inner divertor was being over-loaded. As a result, an inner divertor modification is being installed in C-Mod. The new design is intended to allow a change in profile of the divertor to accommodate a higher plasma triangularity, strengthen the inner vessel wall to survive 9.0 Tesla, 2.5 MA disruptions and, eliminate tile rotation. The thermal differentials between tiles and vessel wall, necessitated the introduction of compliance in the reinforcement hardware. Practical assembly within the vessel required manageable part size,and bolted interfaces which further reduced the strength and stiffness. A modest improvement of 22% was achieved while meeting the many design constraints.

Keywords

fusion reactor design; fusion reactor divertors; Alcator C-Mod; inner divertor; inner vessel wall; plasma triangularity; stiffness; strength; tile rotation; upgrade; Assembly; Contracts; Hardware; Nuclear and plasma sciences; Plasma temperature; Temperature distribution; Thermal expansion; Thermal stresses; Tiles; Tokamaks;

fLanguage

English

Publisher

ieee

Conference_Titel

Fusion Engineering, 2002. 19th Symposium on

Print_ISBN

0-7803-7073-2

Type

conf

DOI

10.1109/FUSION.2002.1027705

Filename

1027705