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First wall and blanket design for the STARFIRE commercial tokamak power reactor

Conference ·
OSTI ID:5532708
The first wall and blanket design concepts being evaluated for the STARFIRE commercial tokamak reactor study are presented. The two concepts represent different approaches to the mechanical design of a tritium breeding blanket using the reference materials options. Each concept has a separate ferritic steel first wall cooled by heavy water (D/sub 2/O), and a ferritic steel blanket with solid lithium oxide breeder cooled by helium. A separate helium purge system is used in both concepts to extract tritium. The two concepts are compared and relative advantages and disadvantages for each are discussed.
Research Organization:
Argonne National Lab., IL (USA)
Sponsoring Organization:
USDOE
DOE Contract Number:
W-31109-ENG-38
OSTI ID:
5532708
Report Number(s):
CONF-791102--127
Country of Publication:
United States
Language:
English