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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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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Fusion Science and Technology
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Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
T. Kanazawa, M. Nishikawa, H. Yamasaki, K. Katayama, H. Kashimura, T. Hanada, S. Fukada
Fusion Science and Technology | Volume 60 | Number 3 | October 2011 | Pages 1167-1170
Blanket and Breeder Materials | Proceedings of the Ninth International Conference on Tritium Science and Technology | doi.org/10.13182/FST11-A12623
Articles are hosted by Taylor and Francis Online.
The present authors have developed the tritium release model to represent the tritium release behavior from solid breeder materials (Li2ZrO3, Li2TiO3, Li4SiO4, LiAlO2 and Li2O). It has been found that water is released from solid breeder materials into the purge gas due to desorption of physically and chemically adsorbed water and water generation reaction and that this water affects the tritium release behavior. In this study, the amount of adsorbed water and its desorption rate for Li2ZrO3 were quantified. It was found in this experiment that Li2ZrO3 has the largest adsorption amount among the solid breeder candidates. It was also observed that Li2ZrO3 has the largest water generation capacity among the solid breeder candidates. A unique reaction at around 550°C which made up approximately 80% of the capacity of water generation was also observed. It is considered that the phase change of ZrO2 at around 550°C supplies oxygen to promote water generation reaction. Tritium release behavior from Li2ZrO3 blanket was estimated using the properties obtained in this study under the operational condition of ITER or a commercial reactor.