Actions for General Atomic noncircular tokamak demonstration power reactor : blanket

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General Atomic noncircular tokamak demonstration power reactor : blanket/shield, tritium and power conversion ststems

Published
United States : [publisher not identified], 1976.
[Oak Ridge, Tennessee] : [U.S. Atomic Energy Commission], 1976.
Physical Description
microfiche : negative ; 11 x 15 cm

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Summary
A reference conceptual design for a noncircular tokamak power reactor has been established and developed in a preliminary form. Since an important objective of the design is that it incorporates technological scaling from experimental power reactor(s), the reference plant has retained certain major design features in common with the noncircular EPR reference conceptual design. The major design parameters of the reactor are given. The reactor has a 7 m major radius and a net electrical output just over 500 MW(e). A primary engineering objective in the design is the minimization of expensive and time-consuming remote maintenance operations by designing the reactor to permit hands-on maintenance externally to the shield system and toroidal field coils. To this end the outboard shield is comprised of low activity materials and flux levels at the toroidal field coils are intentionally reduced to levels well under those based on coil refrigeration and annealing criteria. A conventional steam power conversion cycle is briefly described.
Report Numbers
GA-A-13896; CONF-760343-2
Other Subject(s)
Collection
U.S. Atomic Energy Commission depository collection.
Note
DOE contract number: E(04-3)-167
OSTI Identifier 7178066
Research organization: General Atomics, San Diego, CA (United States).
View MARC record | catkey: 45371733