Fusion Science and Technology / Volume 19 / Number 3P2A / May 1991 / Pages 746-751
Inertial Fusion / dx.doi.org/10.13182/FST91-A29434
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A breeding blanket design for the tritium production ICF reactor SIRIUS-T is presented. The blanket consists of alternating layers of beryllium multiplier and lithium breeder/coolant with vanadium alloy structure. A tritium breeding ratio of 1.9 can be achieved for the optimum layered configuration with lithium enriched to 90% 6Li. An optimum coolant routing scheme is utilized to achieve adequate thermal hydraulics performance. The maximum structural material temperature is 650°C.