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Fusion Science and Technology
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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.
Nermin A. Uckan
Fusion Science and Technology | Volume 14 | Number 2 | September 1988 | Pages 299-319
Technical Paper | Plasma Engineering | doi.org/10.13182/FST88-A20263
Articles are hosted by Taylor and Francis Online.
A simple global analysis is developed to examine the relative merits of size (L = a or R0), field (B0), and current (I) on ignition regimes of tokamaks under various confinement scaling laws. Scalings of key parameters (nτE, β, Paux, Pfus, etc.) with L, B0, and I are presented at several operating points, including (a) optimal path to ignition (saddle point), (b) ignition at minimum beta, (c) ignition at 10 keV, and (d) maximum performance at the limits of density (nmax ∼ B0/R0) and beta (βcrit ∼ I/aB0). Expressions for the saddle point and the minimum conditions needed for ohmic ignition are derived analytically for any confinement model of the form τE ∼ nxTy. For a wide range of confinement models, the “figure of merit” parameters and I are found to give a good indication of the relative performance of the devices, where q* is the cylindrical safety factor. As an illustration, the results are applied to representative “CITs” (a class of compact, high-field ignition tokamaks) and “Super-JETs” [a class of large-size (few × JET), low-field, high-current (≳20-MA) devices].