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Neutronics Analysis of a Self-Cooled Blanket for a Laser Fusion Plant with Magnetic Diversion

M. E. Sawan, C. S. Aplin, G. Sviatoslavsky, I. N. Sviatoslavsky, A. R. Raffray

Fusion Science and Technology / Volume 52 / Number 4 / November 2007 / Pages 771-775

Technical Paper / Nuclear Analysis and Experiments /

A blanket concept made of the low electrical conductivity SiCf/SiC composite and utilizing Li17Pb83 as coolant and tritium breeder has been developed and integrated with the magnetic diversion system. Neutronics issues related to tritium breeding adequacy particularly with the area lost to the dump plates at the ring and point cusps were addressed. Radiation damage and lifetime considerations for the SiCf/SiC structural material were also addressed. Another issue of concern is providing adequate shielding for the superconducting cusp magnets. Detailed neutronics analyses show that tritium self-sufficiency can be achieved. A 0.5 m thick water-cooled steel shield that doubles as the vacuum vessel is a reweldable lifetime component and will provide adequate shielding for the magnets.

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