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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.
Masabumi Nishikawa, Hiroki Takata, Toshiharu Takeishi, Kozo Kamimae
Fusion Science and Technology | Volume 48 | Number 1 | July-August 2005 | Pages 386-389
Technical Paper | Tritium Science and Technology - Tritium Measurement, Monitoring, and Accountancy | doi.org/10.13182/FST05-A949
Articles are hosted by Taylor and Francis Online.
Feasibility of the monitoring way of HTO in air to follow the tritium level in water contained in a small shallow beaker with open surface placed still in a room was discussed in this study. It is considered that the isotope exchange reaction between tritiated water in air and water in a beaker, the evaporation or condensation reaction of water at surface and the diffusion of tritium in water played the important roles in the tritium transfer phenomena through the air-water interface. Using the mass transfer coefficients obtained in the previous paper, change of tritium level in water contained in a shallow open beaker was numerically estimated and comparison with the experimental data showed good agreement. The estimated amount of tritium released from the facility with storage pools of spent fuels from a PWR power station using the method of this study showed good agreement with the observed value evaluated from the monitor of the power station