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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.
T. Hayashi, M. Yamada, T. Suzuki, Y. Matsuda, K. Okuno
Fusion Science and Technology | Volume 28 | Number 3 | October 1995 | Pages 1015-1019
Analysis and Accountancy | 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-A30539
Articles are hosted by Taylor and Francis Online.
A scaled ZrCo bed ( 25 g tritium capacity of design ) with gas flowing calorimetry system was fabricated to establish the “in-bed” tritium accounting technology to apply to the ITER tritium storage beds. The basic calorimetric characteristics, steady state temperature raise of He gas stream flowing through a secondary coil line fixed in the ZrCo tritide, was measured and correlated with power input by heater to simulate tritium decay heat or with actual tritium storage. The target accuracy is 1 % which means to measure +− 1 gram (0.32 watt) of tritium on 100 g storage. The results shows the good accounting function that the temperature increases of He stream of 4.7 and 96.8 degrees were measured under power input of 0.32 and 8.0 watts, respectively, with good reproducibility. These “in-bed” tritium accounting function was well demonstrated storing a gram level of tritium gas within a few days.