Blanket-cooling optimization for the Princeton fusion power reactor
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 study was made for optimizing the design of the cooling system for the breeding blanket of the Princeton reference design model of a fusion power reactor. The constraints observed were compatibility with the overall design of the reactor, use of conventional structural materials, use of eutectic flibe for breeding, and use of helium for heat transfer. The parameters varied were cooling-tube diameter and/or length, cooling-tube wall thickness, coolant pressure, and heat load per tube in high- heat-flux regions. The results of the study indicate that the most satisfactory parameter for optimization was the cooling-tube diameter, and the optimum value was found to be between 2 and 3 cm outer diameter. The other parameters gave optima at limiting constraints. (auth)
- Research Organization:
- Princeton Univ., NJ; Texas Univ., Austin (USA)
- NSA Number:
- NSA-29-030977
- OSTI ID:
- 4327240
- Report Number(s):
- CONF-721111--
- Country of Publication:
- Country unknown/Code not available
- Language:
- English
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