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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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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.
B. W. N. Fitzpatrick, J. W. Davis, A. A. Haasz, A. G. McLean, P. C. Stangeby, S. L. Allen, R. Ellis, W. P. West
Fusion Science and Technology | Volume 58 | Number 2 | October 2010 | Pages 603-612
Technical Paper | doi.org/10.13182/FST10-A10887
Articles are hosted by Taylor and Francis Online.
Carbon-based codeposits formed in carbon-containing fusion devices have the potential to dominate tritium retention in the torus. One of the tritium removal techniques currently being studied is thermo-oxidation, which is unique in its ability to remove tritium from codeposits without mechanical intervention in the torus and in its ability to remove tritium from codeposits in tile gaps and shaded areas. In preparation for an oxidation experiment planned to be performed in DIII-D, we have investigated the potential collateral effects of thermo-oxidation on DIII-D in-vessel components. Laboratory oxidation experiments were performed at 2 Torr ([approximately]270 Pa) and 15 Torr ([approximately]2 kPa) O2 pressure and temperatures in the range 100 to 350°C (373 to 623 K) for 2 to 8 h. After oxidation, components were examined for visual or mechanical change, and when appropriate, mass changes were also obtained. In some cases, optical diagnostics were also performed. The specimens were mostly spare/surplus components and spanned a wide variety of materials and functions, e.g., cryopump components; structural, mechanical, and diagnostic components; and fast-wave antennas. The effect of oxidation was found to be negligible for nearly all DIII-D components and materials tested.