Title :
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
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;
Conference_Titel :
Fusion Engineering, 1993., 15th IEEE/NPSS Symposium on
Conference_Location :
Hyannis, MA
Print_ISBN :
0-7803-1412-3
DOI :
10.1109/FUSION.1993.518532
