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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.
A. Fernández, A. Cappa, F. Castejón, J. M. Fontdecaba, K. Nagasaki
Fusion Science and Technology | Volume 53 | Number 1 | January 2008 | Pages 254-260
Technical Note | Special Issue on Electron Cyclotron Wave Physics, Technology, and Applications - Part 2 | doi.org/10.13182/FST08-A1670
Articles are hosted by Taylor and Francis Online.
Electron cyclotron current drive (ECCD) experiments carried out in the TJ-II stellarator are presented. In all the analyzed plasma discharges, the second-harmonic electron cyclotron resonance heating (ECRH) power is launched on-axis from two low-field-side stellarator symmetric positions. To investigate the ECCD properties of the device, the dependence of the total toroidal plasma current on the launching direction of both ECRH beams at fixed density conditions, and on the line average density for some fixed launching configurations, has been determined. In the launching direction scan, only discharges with similar density and temperature profiles have been studied, in order to avoid strong modifications of the bootstrap current contribution and the refraction properties of the plasma. Moreover, the measurements of the toroidal plasma current and the plasma profiles are taken at the end of the discharge, when approximately steady-state conditions are achieved. Using the normalized current drive efficiency as defined by ECCD [identical] <ne> IECCDR/PECRH, we have obtained values up to ECCD [approximately equal to] 0.001 × 1020 A W-1 m-2.
