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The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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Fusion Science and Technology
February 2024
Latest News
Lightbridge announces first U-Zr fuel rod samples extruded at INL
Lightbridge Corporation announced today that it has reached “a critical milestone” in the development of its extruded solid fuel technology. Coupon samples using an alloy of zirconium and depleted uranium—not the high-assay low-enriched uranium (HALEU) that Lightbridge plans to use to manufacture its fuel for the commercial market—were extruded at Idaho National Laboratory’s Materials and Fuels Complex.
K. Kobayashi, T. Hayashi, Y. Iwai, N. Asanuma, M. Nishi
Fusion Science and Technology | Volume 41 | Number 3 | May 2002 | Pages 673-677
Safety and Safety System | Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001 | doi.org/10.13182/FST02-A22672
Articles are hosted by Taylor and Francis Online.
To construct the ITER with high safety and acceptability, it is very important to grasp the removal behavior of tritium happened to leak in the room, the final confinement barrier. In order to obtain data on tritium removal behavior from atmosphere in a room under the various conditions (humidity, ventilation flow rate), intentional tritium release experiments have been carried out with the Caisson Assembly for Tritium Safety Study (CATS) which consists of 12 m3 gas-tight box (Caisson) for the study of tritium behavior in large space. Effect of adding water vapor has also investigated for effective removal. When the tritiated water existed in the released tritium, residual contamination on the wall of the Caisson was detected under the various ventilation flow rate and it was found that it depended on the initial humidity in the Caisson. On the other hand, when the water vapor was added into the Caisson after found the residual contamination, the residual contamination was removed quickly on the wall of the Caisson. The adding water vapor into the Caisson, it was effective for the tritium removal. Analytical work have also progressed and analyzed tritium removal behavior became to be in good agreement with the experimental results by considering the adsorption and desorption reaction rate of tritiated water on the wall.