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Fusion Science and Technology
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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.
N. T. Kazakovsky, I. A. Abramov, A. I. Vedeneev, M. V. Glagolev, A. A. Selezenev
Fusion Science and Technology | Volume 48 | Number 1 | July-August 2005 | Pages 692-695
Technical Paper | Tritium Science and Technology - Properties, Reactions, and Applications | doi.org/10.13182/FST05-A1018
Articles are hosted by Taylor and Francis Online.
A method and a laboratory facility were developed for the purpose of determining inflammation temperature of hydrogen-oxygen gaseous mixtures (HOGM). We have determined the inflammation temperature of HOGM containing the following impurities: Ar, Xe, H2O and tritium within the range of initial gas pressure from 3 to 13 kPa. The results agree well with the available reference and numerical simulation results. The inflammation temperatures of HOGM in the range of initial gas pressure from 2 to 13 kPa increases from 793 to 873 K. Average inflammation temperatures of hydrogen and deuterium mixtures differ no more than 1.6 %. Introduction of inert gases (argon and xenon) into gaseous mixture up to 45 volume percent does not change inflammation temperature significantly. Water introduction (in the range from 2.4 to 25 volume percent) does not cause gaseous mixture inflammation. The effect of tritium -radiation on temperature of GM inflammation within the range of tritium concentration concerned is insignificant and agrees with the results of numerical modeling obtained earlier.