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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.
Dongxun Zhang, Wei Liu, Yuan Qian, Ji Que
Fusion Science and Technology | Volume 67 | Number 3 | April 2015 | Pages 681-684
Proceedings of TRITIUM 2013 | doi.org/10.13182/FST14-T109
Articles are hosted by Taylor and Francis Online.
Tritium was generated by the interaction of neutrons with the lithium and beryllium in the molten salt reactors (MSRs), which use Flibe as one of solvents of fluoride fuel. Tritium as by-product in the MSRs would be an important safety issue because it could easily diffuse through high temperature heat exchangers into environment. The experimental technique of gas driven permeation was used to investigate the transport parameter of hydrogen in Hastelloy C-276 which was considered as one of the candidate structure materials. The measurements were carried out at the temperature range of 400-800°C with hydrogen loading pressures ranging from 5×103 to 4×104 Pa. The H diffusive transport parameters for Hastelloy C-276 followed an Arrhenius law in this temperature range and were decreased due to the existence of the alloying elements compared with Ni201. The possible reason may be the trapping effects, which were formed by the alloying elements of Mo and Cr in the matrix. At the same time, the thin oxidation layer formed by the high Cr content could lead to the slower dissociation process of H2 at the surface.