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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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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.
Nobuyuki Hosogane, JT-60SA Design Team, Japan-Europe Satellite Tokamak Working Group
Fusion Science and Technology | Volume 52 | Number 3 | October 2007 | Pages 375-382
Technical Paper | The Technology of Fusion Energy - Experimental Devices and Advanced Designs | doi.org/10.13182/FST07-A1516
Articles are hosted by Taylor and Francis Online.
The JT-60SA (Super Advanced) project is a joint project of the ITER Satellite Tokamak program and the National Centralized Tokamak program in Japan with missions of supporting ITER, complementing ITER and exploring advanced issues toward DEMO. JT-60SA is a tokamak with superconducting coils, equipped with a poloidal field coil system with wide plasma shape controllability, upper and lower divertors with different shapes, NBI and ECRF with heating power 41 MW and various heating methods, in-vessel coils for suppressing MHD instabilities. With these functions, possibilities of producing ELMy H-mode with improved confinement, full non-inductive current drive of high beta plasmas (N=3.7 at IP=3.5 MA, N =4.4 at IP=2.4 MA) and break-even class plasmas necessary for accomplishing the mission have been confirmed. The engineering design of JT-60SA is being done taking large annual neutron production into account. Double skin walls filled with borated water or boron doped concrete are employed for the vacuum vessel and cryostat, respectively, for neutron shield. Divertors structures and first walls are being designed so as to be changed with remote handling systems in the high radiation circumference.
