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Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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.
Hunter Andrews, Supathorn Phongikaroon
Nuclear Technology | Volume 206 | Number 4 | April 2020 | Pages 651-661
Technical Note | doi.org/10.1080/00295450.2019.1670009
Articles are hosted by Taylor and Francis Online.
Cyclic voltammetry (CV) was used to study SmCl3 at concentrations of 0.42 to 8.99 wt% in molten eutectic LiCl-KCl (44.2:55.8 wt%) at 773 K. For each sample, CV was repeated at different electrode surface areas to measure the peak current density. By analyzing the measured peak current density and concentration relationship with the Randles-Sevcik equation, the Sm(III) diffusivity for each sample was calculated. These diffusion coefficients ranged from 0.934 × 10−5 to 1.572 × 10−5 cm2‧s−1, showing no noticeable trend with a change in concentration. The samples were then divided into two groups of five. The first group was used to develop a calibration model for concentration prediction, while the second group was used to test and validate the model. The first model was based on the relationship between current density and concentration. This model had a very low limit of detection of 0.14 wt% and very low error as evaluated by the root-mean-square error of calibration of 0.108 wt%. The second model was a multivariate approach utilizing the current density values and laser-induced breakdown spectroscopy (LIBS) intensities as regressors; however, the introduction of LIBS data showed an increase in the model’s prediction error when compared to the first model. The electrode withdrawal method proved to be a preferable option due to a substantial increase in precision.