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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. Sugai, M. Yahagi, H. Hamanaka, K. Kuriyama, T. Hshimoto
Fusion Science and Technology | Volume 41 | Number 3 | May 2002 | Pages 1030-1034
Blanket Material and Process | Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001 | doi.org/10.13182/FST02-A22740
Articles are hosted by Taylor and Francis Online.
In the Japan Atomic Energy Research Institute (JAERI), technology for tritium production by use of 6LiAl alloy has been developed with the aim of furnishing tritium for fusion research. The alloy contains β-phase, i.e., intermetallic compound β-LiAl, which has a large influence on the tritium behavior in 6Li-Al alloy. Since β-LiAl has a unique crystal structure and a large amount of Li vacancy at room temperature, the tritium behavior in β-LiAl is affected by the defect structure and the lithium diffusion. In this paper, on the basis of a simultaneous measurement of tritium release rate and electrical reseistivity, it is suggested that the tritium diffusion has a strong correlation with the lithium diffusion in the neutron-irradiated β-6LiAl.
