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November 9–12, 2025
Washington, DC|Washington Hilton
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Researchers use one-of-a-kind expertise and capabilities to test fuels of tomorrow
At the Idaho National Laboratory Hot Fuel Examination Facility, containment box operator Jake Maupin moves a manipulator arm into position around a pencil-thin nuclear fuel rod. He is preparing for a procedure that he and his colleagues have practiced repeatedly in anticipation of this moment in the hot cell.
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.