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Latest News
New X-ray imaging for ITER-supporting tokamaks
As researchers continue to seek ways to better understand the plasma inside fusion machines to fully harness fusion energy, Princeton Plasma Physics Laboratory is leading a project to provide new X-ray imaging systems to two international tokamak projects: WEST, in southern France, and JT-60SA, in Japan—both of which are designed to support the development of ITER.
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.
