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2025 ANS Winter Conference & Expo
November 8–12, 2025
Washington, DC|Washington Hilton
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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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Nuclear News 40 Under 40—2025
Last year, we proudly launched the inaugural Nuclear News 40 Under 40 list to shine a spotlight on the exceptional young professionals driving the nuclear sector forward as the nuclear community faces a dramatic generational shift. We weren’t sure how a second list would go over, but once again, our members resoundingly answered the call, confirming what we already knew: The nuclear community is bursting with vision, talent, and extraordinary dedication.
Yohei Ozeki, Yuji Hatano, Haruka Taniguchi, Masao Matsuyama
Fusion Science and Technology | Volume 60 | Number 4 | November 2011 | Pages 1499-1502
Interaction with Materials | Proceedings of the Ninth International Conference on Tritium Science and Technology (Part 2) | doi.org/10.13182/FST11-A12716
Articles are hosted by Taylor and Francis Online.
Sheet type specimens of type 316 stainless steel covered by Cr oxide layers were exposed to tritium gas at 300 °C together with the specimens covered by Fe-rich oxide layers and pure Fe specimens to compare tritium behaviors in oxide films with different Cr contents. Tritium concentration in the oxide layers decreased with increasing Cr content due to reduction in concentrations of hydroxyl species and adsorbed water. In addition, release rate of tritium from Cr oxide layers was larger than that from Fe-rich oxide layers. It was concluded that preparation of thin Cr oxide layer is effective to reduce surface tritium contamination of austenitic stainless steels.