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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.
Wei Ding, Eckhard Krepper, Uwe Hampel
Nuclear Technology | Volume 205 | Number 1 | January-February 2019 | Pages 23-32
Technical Paper | doi.org/10.1080/00295450.2018.1496693
Articles are hosted by Taylor and Francis Online.
In this work, we report on the development of a time-averaged Eulerian multiphase approach applied in the wall boiling process especially in the forced convective boiling process. Recently, in order to obtain accurate bubble dynamics and reduce case dependency, a single bubble model for nucleate boiling based on known published models was developed. The model considers geometry change and dynamic contact and inclination angles during bubble growth. The model has good agreement with experiments. However, the predicted bubble dynamics is dependent on the wall superheat (cavity activation temperature). This single bubble model requires an update of the current nucleation site activation and heat flux partitioning models in time-averaged Eulerian multiphase approaches. In this work, we will introduce this implementation in detail. Further, with help of the MUSIG (MUltiple SIze Group) model and a breakup and coalescence model, the time-averaged Eulerian approach could simulate the bubble size distribution in a heated pipe. With the necessary calibration of the nucleation site density, the comparisons between the calculation results and Bartolomei et al.’s experiments demonstrate the success of the implementation and the accuracy of this approach.