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2026 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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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
November 2025
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Education and training to support Canadian nuclear workforce development
Along with several other nations, Canada has committed to net-zero emissions by 2050. Part of this plan is tripling nuclear generating capacity. As of 2025, the country has four operating nuclear generating stations with a total of 17 reactors, 16 of which are in the province of Ontario. The Independent Electricity System Operator has recommended that an additional 17,800 MWe of nuclear power be added to Ontario’s grid.
Masayuki Tokitani, Yukinori Hamaji, Yutaka Hiraoka, Yuki Hayashi, Suguru Masuzaki, Hitoshi Tamura, Hiroyuki Noto, Teruya Tanaka, Tatsuya Tsuneyoshi, Yoshiyuki Tsuji, Gen Motojima, Hiromi Hayashi, Takanori Murase, Takeo Muroga, Akio Sagara, Tomohiro Morisaki
Fusion Science and Technology | Volume 79 | Number 6 | August 2023 | Pages 651-661
Research Article | doi.org/10.1080/15361055.2023.2176184
Articles are hosted by Taylor and Francis Online.
A novel method, called Advanced Multi-Step Brazing, was developed to fabricate a new type of divertor heat removal component with W armor and an oxide-dispersion-strengthened copper (GlidCop®) heat sink in the initial phase of our work. Later, a new type of divertor heat removal component, which has a rectangular-shaped cooling channel with a V-shaped staggered-rib structure in the GlidCop heat sink, was developed. This new component showed an extremely high heat removal capability during a ~30 MW/m2 steady-state heat loading condition in our previous work. In this work, the new component was installed in the divertor strike position of the Large Helical Device and exposed to neutral beam injection–heated plasma discharges with 1180 shots (~8000 s) in total. Though submillimeter-scale damage, such as unipolar arc trails and microscale cracks, was identified on the W surface, the extremely high heat removal capability did not show any sign of degradation over the experimental period. On the other hand, remarkable sputtering erosion and redeposition phenomena, due to the strong influx of the divertor plasma, was confirmed on the W armor.