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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.
S. H. Son, K. M. Song, S. K. Lee, K. W. Lee, B. W. Ko
Fusion Science and Technology | Volume 60 | Number 3 | October 2011 | Pages 1105-1108
Concept and Facility | Proceedings of the Ninth International Conference on Tritium Science and Technology | doi.org/10.13182/FST11-A12608
Articles are hosted by Taylor and Francis Online.
The tritium metering, assay, recovery and storage (TriMARS) facility of KEPCO Research Institute has been installed to develop expertise in the tritium handling technology and to support the tritium control system in Korea. The major systems and equipment of the facility consisted of a tritium assaying and dispensing system, a tritium recovery system, a purge gas recombiner system, a tritium calorimeter, a gas chromatograph, tritium monitors, a high integrity glove box and air purged enclosures. The annual tritium usage is restricted below 11.5 PBq of tritium. The tritium dispensing and loading would be carried out by batch transfers. Tritium metering is based on accurate pressure-volume-temperature measurements and GC analysis. Three metering tanks were provided to measure 0.37 TBq to 185 TBq of T2 gas at sub-atmospheric pressure. Three uranium beds were installed to store tritium from outside and to recover the tritium residual of process equipment in the facility. Tritium recovery systems, secondary enclosures and tritium monitors were provided to protect workers from tritium exposure. For tritium accountancy for all shipments in and out at the facility, a dedicated twin cell tritium calorimeter was installed and demonstrated.