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Waste management of first wall and blanket structural materials for tokamak fusion reactors

Conference · · Nucl. Technol./Fusion; (United States)
OSTI ID:6184185
A comparison has been made of the induced radioactivities in the first wall and structural materials of the breeder blanket in the high flux region for two different fusion reactor types. One system is the STARFIRE, a tokamak reactor with PCA, a modified stainless steel, as a first wall and a LiA10/sub 2/ breeder blanket; the other is a reactor based on the STARFIRE design with a vanadium alloy as the first wall and structural material, and circulating molten lithium as the breeder/ coolant. The recycling or disposal of these structural materials is evaluated.
Research Organization:
Argonne National Lab., 9700 S. Cass Avenue, Argonne, IL 60439
OSTI ID:
6184185
Report Number(s):
CONF-830406-
Conference Information:
Journal Name: Nucl. Technol./Fusion; (United States) Journal Volume: 4:2
Country of Publication:
United States
Language:
English