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

Conference ·
OSTI ID:6423454

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 LiAlO/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., IL (USA)
DOE Contract Number:
W-31109-ENG-38
OSTI ID:
6423454
Report Number(s):
CONF-830406-22; ON: DE83010770
Country of Publication:
United States
Language:
English