Lithium cooling for a low-beta Tokamak reactor
Conference
·
OSTI ID:4306438
From internationai 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 conceptual blanket design, based on lithium coolant, is proposed for a D-T fusion reactor. The reactor is a Tokamak made of 316 stainless steel, with major and minor radii of 12.5 and 2.8 m, respectively. The maximum magnetic field is 86 kG. The nominal wall loading is 0.85 MW/m/sup 2/, and the maximum temperature on the first wall is 500 deg C. The flow configuration is a compromise between power consumption and thermal efficiency. The power required for pumping is moderate, and some power is sacrificed to reduce thermal-feedback problems. The magnetic field is used to control the flow distribution within the blanket. The effects of thermal stress and hoop stress in the first wall are considered. (auth)
- Research Organization:
- Univ. of Wisconsin, Madison; Texas Univ., Austin (USA)
- NSA Number:
- NSA-29-030980
- OSTI ID:
- 4306438
- Report Number(s):
- CONF-721111--
- Country of Publication:
- Country unknown/Code not available
- Language:
- English
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