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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.
Michael T. Tobin
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 763-769
Inertial Fusion | doi.org/10.13182/FST91-A29437
Articles are hosted by Taylor and Francis Online.
A preliminary neutronics analysis of the HYLIFE-II reactor concept gives a tritium breeding ratio of 1.17 and a system energy multiplication factor of 1.14. Modified SS-316 (in which Mn is substituted for Ni) is superior to Hastelloy X and Hastelloy N as a first-wall material considering He generation, dpa-limited lifetime, and shallow-burial index. Since Flibe is corrosive to Mn metals, however, a favorable first-wall material is yet to be decided on. Flibe impurities considered (e.g., inherent impurities and those arising from wall erosion or secondary-coolant leakage) do not increase the hazard to the public over that of pure Flibe. The main issues for HYLIFE-II are the high shallow-burial index (106) and the requirement to contain some 99.7% of the 18F inventory to prevent its release to the public.