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Preliminary conceptual design of a Tokamak reactor

Conference ·
OSTI ID:4306399
From international meeting on the technology of controlled thermonuclear fusion experiments and the engineering aspects of fusion reactors; Austin, Texas, USA (20 Nov 1972). In technology of controlled thermonuclear fusion experiments and the engineering aspects of fusion reactors. A scoping design was carried out to determine the technological problems associated with the low-beta Tokamak approach to reactors. This system is envisioned to operate at quasi-steady state, producing about 1000 MW(th) and using stainless steel and a wall loading of 0.85 MW/m/sup 2/. Various system aspects of the design are described, including the plasma and its control; a diverter and startup magnet system; a blanket, shield, and heatremoval system; toroidal magnet design and limiting stresa effects; and an analysis of system hazards. (auth)
Research Organization:
Univ. of Wisconsin, Madison; Texas Univ., Austin (USA)
NSA Number:
NSA-29-030983
OSTI ID:
4306399
Report Number(s):
CONF-721111--
Country of Publication:
Country unknown/Code not available
Language:
English