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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.
Y.-Z. Wei, K. Takeshita, M. Shimizu, M. Kumagai, Y. Takashima, S. Matsumoto
Fusion Science and Technology | Volume 28 | Number 3 | October 1995 | Pages 1585-1590
Tritium Waste Management and Discharge Control | Proceedings of the Fifth Topical Meeting on Tritium Technology In Fission, Fusion, and Isotopic Applications Belgirate, Italy May 28-June 3, 1995 | doi.org/10.13182/FST95-A30638
Articles are hosted by Taylor and Francis Online.
Deactivation of a hydrophobic Pt/SDBC catalyst for the H2/HTO isotopic exchange reaction used to remove tritium from the waste water generated in a nuclear-fuel reprocessing plant has been studied experimentally. The catalyst was poisoned reversibly by a small amount of HN03 and could be regenerated by washing with water followed by drying in an inert gas. As a countermeasure against this poisoning, the neutralization of the waste water was found to be effective. The presence of I2 in the waste water caused a sharp decrease in the activity of the catalyst, due to the irreversible adsorption of I2 onto the catalyst surface. The I2 poisoning could be prevented by the conversion of I2 into I− or IO3− by neutralization or redox reaction. TBP and the neutral nitrate salts of fission products such as Sr(NO3)2 showed negligible poisoning effects on the catalyst.
