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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.
John A. Schmidt, D. Bruce Montgomery, the CIT Design Team
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 594-598
Overview | doi.org/10.13182/FST91-A29411
Articles are hosted by Taylor and Francis Online.
The Compact Ignition Tokamak (CIT) has been proposed for construction contiguous to the TFTR facility at Princeton Plasma Physics Laboratory. A national design team comprising U.S. fusion laboratories and industry has been organized to design the CIT tokamak. The mission of the CIT Project is to determine the physical behavior of self-heated fusion plasmas, and demonstrate the production of substantial amounts of fusion power. Compact, high-field tokamaks, such as CIT, are ideally suited to study burning plasmas. The basic characteristics of high-field, burning plasmas in general and the CIT device in particular, are high performance derived from high plasma current and high magnetic field, moderate pulse length (10 sec) and lower duty factor.