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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.
Wang-Kee In, Tae-Hyun Chun, Chang-Hwan Shin, Dong-Seok Oh
Nuclear Technology | Volume 161 | Number 1 | January 2008 | Pages 69-79
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT08-A3914
Articles are hosted by Taylor and Francis Online.
A series of computational fluid dynamics (CFD) simulations has been conducted to analyze the heat transfer enhancement in a fully heated rod bundle with mixing-vane spacers. The predicted Nusselt numbers downstream of the split-vane spacer are compared with the available experimental measurements and with correlation. The CFD calculations at Re = 28000 and 42000 showed a lower heat transfer enhancement close to the space grid but a good agreement of the decay rate with the fully heated experimental data at ~6Dh downstream of the grid. The CFD simulations also showed a maximum enhancement of the heat transfer at 6 to 7Dh downstream of the split-vane spacer due to the multiple vortices predicted near the spacer. In addition, the present paper compares the thermal-hydraulic performance of two different mixing vane spacers, i.e., a split-vane spacer and a hybrid-vane spacer, based on CFD simulations at a pressurized water reactor's operating conditions. The split vane is predicted to have a higher overall heat transfer enhancement but a lower local heat transfer far downstream of the spacer where the minimum departure from nucleate boiling ratio is anticipated.