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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.
Hangbok Choi, Bo W. Rhee, Hyunsoo Park
Nuclear Science and Engineering | Volume 126 | Number 1 | May 1997 | Pages 80-93
Technical Paper | doi.org/10.13182/NSE97-A24459
Articles are hosted by Taylor and Francis Online.
Physics studies have been performed for the compatibility of DUPIC fuel design to the existing CANDU-6. The DUPIC fuel is made of spent pressurized water reactor fuel through a dry process, and the bundle design utilizes an advanced CANDU fuel bundle geometry that is mechanically compatible with the current fuel channel and refueling system. The characteristics of a DUPIC core are compared to the current operation limits and performances of a natural uranium core. The refueling simulations have shown that the channel and bundle powers are well below the operation limits for the two- and four-bundle shift refueling schemes. The fuel performance parameters during the refueling operation reserve enough margin to the stress corrosion cracking threshold of natural uranium fuel. With the aid of burnable poison material in the fuel, the safety performance of a DUPIC core is made comparable to that of a natural uranium core. The details of DUPIC fuel design and analysis are described.