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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.
E. S. Bettis, W. B. Cottrell, E. R. Mann, J. L. Meem, G. D. Whitman
Nuclear Science and Engineering | Volume 2 | Number 6 | November 1957 | Pages 841-853
Technical Paper | doi.org/10.13182/NSE57-A35497
Articles are hosted by Taylor and Francis Online.
The ARE was operated successfully in November, 1954, at various power levels up to 2.5 Mw. The maximum steady-state fuel temperature was 1580°F, and there was a differential temperature between the inlet and outlet in the NaF-ZrF4-UF4 fuel of 355°F. The fuel system was in operation for 241 hr before the reactor first became critical and the nuclear operation extended over a period of 221 hr. The final 74 hr of operation were in the megawatt range and resulted in the production of 96-Mwhr of nuclear energy. Effects of various transient conditions on reactor operation were determined.