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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.
J. Chêne, P. Trabuc, O. Gastaldi
Fusion Science and Technology | Volume 54 | Number 2 | August 2008 | Pages 510-514
Technical Paper | Materials Interactions | doi.org/10.13182/FST08-A1865
Articles are hosted by Taylor and Francis Online.
The behavior of hydrogen and its isotopes in materials is a major concern in future nuclear systems both for the predictive analysis of the role of H, D, T in the environmental degradation of structural materials, for the confinement and inventory of tritium, and for the management of tritiated wastes.This study is focused on the characterization of the effect of the alloy microstructure, of desorption anneal and of oxide films on the tritium behavior (desorption kinetics, trapping, residual concentration) in various austenitic stainless steels.Different techniques (high temperature extraction of hydrogen, beta counting of tritium in massive samples) were used to study : the tritium absorption and desorption in several stainless steels, the role of the annealing conditions (temperature/time) on the tritium residual concentration and desorption flow, and the role of microstructural defects and of oxide films on the diffusion and trapping of tritium.