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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.
Mireia Piera, José M. Martinez-Val
Fusion Science and Technology | Volume 10 | Number 3 | November 1986 | Pages 1321-1326
Fusion Application | doi.org/10.13182/FST86-A24913
Articles are hosted by Taylor and Francis Online.
An analytical characterization of the neutronics of a hybrid blanket is used to determine the regimes of tritium production. A set of fundamental parameters is identified as the basis of this characterization, which enables one to set an upper bound for the number of tritium atoms produced per nuclear fusion. This upper bound depends mainly on η - the mean number of secondary neutrons per absorption in the fuel of the blanket - and it is found out the requirement of a value η>l for reaching tritium breeding.