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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.
M. Tokitani, N. Yoshida, M. Miyamoto, T. Hino, Y. Nobuta, S. Masuzaki, N. Ashikawa, A. Sagara, N. Noda, H. Yamada, A. Komori, LHD Experiment Group
Fusion Science and Technology | Volume 58 | Number 1 | July-August 2010 | Pages 305-320
Chapter 7. Plasmas-Wall Interactions | Special Issue on Large Helical Device (LHD) | doi.org/10.13182/FST10-A10817
Articles are hosted by Taylor and Francis Online.
The Large Helical Device (LHD) has been equipped with movable- and fixed-type material probe systems. Characterization studies of surface modifications on plasma-facing components (PFCs) have been actively progressing by using these probes. After exposure of the PFCs to the plasma, various kinds of surface analysis were conducted. The first walls and divertor tiles of LHD are made of stainless steel and isotropic graphite (IG-430U, Toyo Tanso Co., Ltd.), respectively. They are frequently exposed not only to high-power pulsed main discharges but also to wall-conditioning processes such as glow discharge cleaning (GDC). Thus, the surfaces of the PFCs are drastically changed due to sputtering erosion, impurity deposition, and melting damage. Graphite divertor tiles are eroded primarily during the main discharges; the eroded carbon migrates and deposits on the first-wall surfaces, particularly near the divertor array. First walls are eroded mainly during GDC, which significantly changes the condition of the PFCs. During the main discharges, the majority of incidence particles to the first wall are energetic neutrals (CX neutrals) generated by charge-exchange collisions. Studies of the material damage caused by CX neutrals also have been done. In this paper, the characteristics of surface modifications of PFCs by means of material probe experiments and subsequent surface analysis are summarized.