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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.
M. A. Shinaishin, M. A. Abolfadl, A. S. Khedr, M. M. Kamel
Nuclear Science and Engineering | Volume 136 | Number 3 | November 2000 | Pages 376-387
Technical Paper | doi.org/10.13182/NSE00-A2166
Articles are hosted by Taylor and Francis Online.
This work aims at simulating steam Zircaloy clad interaction in a wide range of temperatures extending to those expected in severe accident conditions of nuclear power plant light water reactors. The equations governing interaction variables for a two-layer (-oxide) and three-layer (--oxide) structure are analytically solved for a semi-infinite and for a finite metal thickness. This method has great computational advantages (small calculation time with no divergence problem) compared with the numerical solution methods, and it can be accurately applied at high temperatures and for finite metal thickness compared to published parabolic correlations, which yield large deviations from experimental data at these conditions. Variables such as oxidation rates, steam consumption, hydrogen generation, and heat released due to oxidation are very important in identifying reactor core degradation scenarios. We thus focused on predicting them as accurately as possible. The predicted oxidation rates at constant temperatures and under constant heating rates are compared with available experimental data for Zircaloy-4, and good agreements were observed. The results reflect the importance of the oxidation heat generation as a heat source in severe accidents knowing that the reactor core contains large quantities of structural metals.