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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.
C. J. Oblinger, H. A. Dube
Nuclear Science and Engineering | Volume 11 | Number 3 | November 1961 | Pages 263-266
Technical Paper | doi.org/10.13182/NSE61-A26001
Articles are hosted by Taylor and Francis Online.
A diffusion coefficient for hydrogen in ingot uranium was determined at 800°C on 1-in. long slug blanks. A value of 14.2 × 10−5 cm2/sec was obtained from 15 determinations. The precision of the average value at the 95% confidence level was ±3.6%. Three methods of cleaning (preparatory to analysis) were employed, no bias being detected among them. An equation was used to calculate the total gas dissolved in a sample by measuring the gas evolved after a short time and using the diffusion coefficient. In a comparison of the total evolved gas (3-hr extraction) with the calculated total gas (½-hr extraction), an error of < ± 2% was obtained from 15 samples.