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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.
Ralph M. Singer, Jerry L. Gillette, Gerald H. Golden, Dale Mohr, Wayne K. Lehto, Charles C. Price, John I. Sackett
Nuclear Science and Engineering | Volume 63 | Number 1 | May 1977 | Pages 75-82
Technical Paper | doi.org/10.13182/NSE77-A27006
Articles are hosted by Taylor and Francis Online.
The Experimental Breeder Reactor II is a sodium-cooled fast breeder reactor and is designed to operate at a thermal power of 62.5 MW and an electrical generation rate of 20 MW. In a continuing program devoted to the understanding of the thermal, hydraulic, and neutronic behavior of this reactor under both normal and off-normal operating conditions, a series of steady-state natural convection tests have been conducted. Instrumentation utilized for the control and observation of the reactor behavior during these experiments included both the normal plant sensors as well as those located in-core within a special fueled subassembly. The results of these measurements have been compared to the predictions of an analytical model of the entire primary heat transport circuit and satisfactory agreement was obtained.