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Pacific Fusion pulsed-power facility to host external users
Concept art of Pacific Fusion’s demonstration system. (Image: Pacific Fusion)
Pacific Fusion is preparing to start construction on a pulsed-power inertial fusion facility in New Mexico, and today the company announced it is seeking expressions of interest from researchers in industry, academia, and government who may want to run experiments at the facility.
M. E. Sawan, E. A. Mogahed
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 746-751
Inertial Fusion | doi.org/10.13182/FST91-A29434
Articles are hosted by Taylor and Francis Online.
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.