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Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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Fusion Science and Technology
August 2025
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Industry Update—August 2025
Here is a recap of industry happenings from the recent past:
SMR service center targeted for Ontario
GE Vernova Hitachi Nuclear Energy has announced plans to invest as much as $50 million to establish a Canadian BWRX-300 Engineering and Service Center near Ontario Power Generation’s Darlington New Nuclear Project site. The Ontario government had previously approved the construction of the first of four BWRX-300 small modular reactors at the site. The center will provide engineering and technical services for the long-term operation and maintenance of the future fleet of SMRs in Ontario. It will also serve as a hub for innovation and training, knowledge sharing, supply chain engagement, and workforce development.
K. Hoshino, T. Suzuki, A. Isayama, S. Ide, H. Takenaga, H. Kubo, T. Fujita, Y. Kamada, T. Fujii, T. Tsuda, JT-60 Team, K. Ida, S. Inagaki
Fusion Science and Technology | Volume 53 | Number 1 | January 2008 | Pages 114-129
Technical Paper | Special Issue on Electron Cyclotron Wave Physics, Technology, and Applications - Part 2 | doi.org/10.13182/FST08-A1659
Articles are hosted by Taylor and Francis Online.
The application of the electron cyclotron heating (ECH) and electron cyclotron current drive (ECCD) to the JT-60U tokamak started in 1999. Because the power deposition by the electron cyclotron wave is very localized and controllable, the application of ECH/ECCD has been very attractive for the following recent studies in the JT-60U: (a) the extension of plasma performance toward high normalized beta (N), (b) high bootstrap current fraction, and (c) long-pulse operation (65 s). Plasma produced in the studies aiming at advanced steady tokamak is considered to be in a kind of "self-organized state" with external input power by joule heating plus additional heating. The internal transport barrier that develops by the additional heating enhances the local bootstrap current by steep pressure gradient, and then the modified plasma current profile establishes a different confining poloidal magnetic field configuration from the initial configuration. In such experimental research in the JT-60U, the ECH contributes as an active tool for the plasma control to study the physical mechanisms of high- magnetohydrodynamic instability, internal transport barrier, current hole, and so on. Results of the ECH/ECCD applications in the JT-60U are briefly reviewed.