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Fusion Science and Technology
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Glass strategy: Hanford’s enhanced waste glass program
The mission of the Department of Energy’s Office of River Protection (ORP) is to complete the safe cleanup of waste resulting from decades of nuclear weapons development. One of the most technologically challenging responsibilities is the safe disposition of approximately 56 million gallons of radioactive waste historically stored in 177 tanks at the Hanford Site in Washington state.
ORP has a clear incentive to reduce the overall mission duration and cost. One pathway is to develop and deploy innovative technical solutions that can advance baseline flow sheets toward higher efficiency operations while reducing identified risks without compromising safety. Vitrification is the baseline process that will convert both high-level and low-level radioactive waste at Hanford into a stable glass waste form for long-term storage and disposal.
Although vitrification is a mature technology, there are key areas where technology can further reduce operational risks, advance baseline processes to maximize waste throughput, and provide the underpinning to enhance operational flexibility; all steps in reducing mission duration and cost.
H. Yamasaki, K. Kashimura, T. Kanazawa, K. Katayama, N. Yamashita, S. Fukada, M. Nishikawa
Fusion Science and Technology | Volume 60 | Number 3 | October 2011 | Pages 1151-1154
Blanket and Breeder Materials | Proceedings of the Ninth International Conference on Tritium Science and Technology | doi.org/10.13182/FST11-A12619
Articles are hosted by Taylor and Francis Online.
It is observed that a fair amount of physical and chemical adsorbed water is released from solid breeder materials by introduction of dry N2 gas and that not a little amount of water is also continuously produced by the water formation reaction when the purge gas with hydrogen is applied. It is reported by present authors that the water released to the purge gas from solid breeder materials affects the tritium release behavior. The capacity and desorption rate of chemical adsorbed water, and the capacity and rate of water formation reaction for Li4SiO4, which has been supplied from FzK, are quantified in this study. It is found that the overall reaction rate of water formation on Li4SiO4 is larger than the rate observed for other solid breeder materials. Therefore, most hydrogen added to the blanket purge gas changes to water so far as the water formation capacity of Li4SiO4 remains. It is also found that water formation capacity of Li4SiO4 is almost the same as that of Li2TiO3. Tritium release behavior from Li4SiO4 and Li2TiO3 packed in the blanket are compared in this paper using the Kyushu University model and properties obtained in this study.