Methodology for first wall design

Author

Galambos, J.D. ; Conner, D.L. ; Goranson, P.L. ; Lousteau, D.C. ; Williamson, D.E. ; Nelson, B.E. ; Davis, F.C.

Author_Institution

Oak Ridge Nat. Lab., TN, USA

Volume

2

fYear

1993

fDate

11-15 Oct 1993

Firstpage

1177

Abstract

An analytic parametric scoping tool has been developed for application to first wall (FW) design problems. Both thermal and disruption force effects are considered. For the high heat flux and high disruption load conditions expected in the International Thermonuclear Experimental Reactor (ITER) device, vanadium alloy and dispersion-strengthened copper offer the best stress margins using a somewhat flattened plasma-facing configuration. Ferritic steels also appear to have an acceptable stress margin, whereas the conventional stainless steel 316 does not appear feasible. If a full semicircle shape FW is required, only the vanadium and ferritic steel alloy have acceptable solutions

Keywords

Tokamak devices; fusion reactor design; fusion reactor materials; fusion reactors; stainless steel; steel; stress analysis; thermal stresses; vanadium alloys; 316 stainless steel; Cu; ITER; International Thermonuclear Experimental Reactor; V alloy; design; dispersion-strengthened Cu; disruption force; ferritic steel; first wall; parametric scoping tool; thermal effects; Coolants; Copper; Equations; Laboratories; Plasma temperature; Process design; Solid modeling; Steel; Thermal force; Thermal stresses;

fLanguage

English

Publisher

ieee

Conference_Titel

Fusion Engineering, 1993., 15th IEEE/NPSS Symposium on

Conference_Location

Hyannis, MA

Print_ISBN

0-7803-1412-3

Type

conf

DOI

10.1109/FUSION.1993.518532

Filename

518532