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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.
L. V. Hampton, G. J. Licina, P. Roy
Nuclear Technology | Volume 52 | Number 3 | March 1981 | Pages 431-434
Technical Note | Material | doi.org/10.13182/NT81-A32718
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The isothermal corrosion of Cr—1 Mo steel in superheated steam is approximated by the linear relationship W = W0 + Rt, where W0 and R are constants exhibiting inverse temperature dependences. Heat flux is accounted for by applying a constant factor of 1.5 to the corrosion rate of any isotherm. No correlation for corrosion in alkaline, deoxygenated water is offered, since data are sparse. Data indicate that, in an evaporator, Cr—l Mo steel corrodes at a rate of ∼2.5 × 10−3 cm/yr.