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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.
J. T. Birkholzer, N. Halecky, S. W. Webb, P. F. Peterson, G. S. Bodvarsson
Nuclear Technology | Volume 163 | Number 1 | July 2008 | Pages 147-164
Technical Paper | High-Level Radioactive Waste Management | doi.org/10.13182/NT08-A3978
Articles are hosted by Taylor and Francis Online.
In heated drifts such as those designated for emplacement of radioactive waste at the proposed geologic repository at Yucca Mountain, temperature gradients cause natural-convection processes that may significantly influence the moisture conditions in the drifts and in the surrounding fractured rock. Large-scale convection cells in the heated drifts would provide an effective mechanism for turbulent mixing and axial transport of vapor generated from evaporation of pore water in the nearby formation. As a result, vapor would be transported from the elevated-temperature sections of the drifts into cool end sections (where no waste is emplaced), would condense there, and subsequently would drain into underlying rock units. To study these processes, we have developed a new simulation method that couples existing tools for simulating thermal-hydrological conditions in the fractured formation with a module that approximates turbulent natural convection in heated emplacement drifts. The new method simultaneously handles (a) the flow and energy transport processes in the fractured rock, (b) the flow and energy transport processes in the cavity, and (c) the heat and mass exchange at the rock-cavity interface. An application is presented studying the future thermal-hydrological conditions within and near a representative waste emplacement drift at Yucca Mountain. Particular focus is on the potential for condensation along the emplacement section, a possible result of heat output differences between individual waste packages.