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2024 ANS Annual Conference
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Las Vegas, NV|Mandalay Bay Resort and Casino
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Fusion Science and Technology
Latest News
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.
S. Keniley, D. Curreli
Fusion Science and Technology | Volume 71 | Number 1 | January 2017 | Pages 93-102
Technical Paper | doi.org/10.13182/FST16-117
Articles are hosted by Taylor and Francis Online.
We present an innovative coupled Boltzmann–binary collision approximation (BCA) method for the simulation of the near-wall plasma in the presence of a material-releasing wall. The method is based on a full-f multispecies Boltzmann solver for the plasma (charged and neutral species) coupled to a modification of the classical BCA code TRIDYN. Both the plasma ions and the impurities are treated as Boltzmann kinetic species, allowing high resolution even at very disparate densities, particle fluxes, drift velocities, and energy fluxes. From the distribution functions, all the fluid moments (density, heat flux, etc.) and the net and gross erosion rates are derived. An example of calculation of a helium plasma facing a beryllium wall is reported, showing the evolution of the phase-spaces of ions, neutrals, and material impurities in the near-wall region at nominal ITER conditions.