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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.
K. Hashizume, T. Tanabe
Fusion Science and Technology | Volume 60 | Number 3 | October 2011 | Pages 1135-1138
Blanket and Breeder Materials | Proceedings of the Ninth International Conference on Tritium Science and Technology | doi.org/10.13182/FST11-A12615
Articles are hosted by Taylor and Francis Online.
In order to determine effective charge Z* of tritium in V-4Cr-4Ti alloy, an electromigration experiment has been carried out at temperatures of 330, 373 and 423 K in an electric field strength of about 5 V/m. Tritium concentration profile in a steady state was measured with an imaging plate (IP) technique. According to a simple electromigration theory, the effective charge Z* of tritium was determined from the tritium profiles. Z* obtained increases from 0.7 to 0.95 with increasing temperature. Comparison with the value of Z* for pure V is made and influences of alloying elements on tritium electromigration are discussed.