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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.
Masao Matsuyama, Masanori Hara
Fusion Science and Technology | Volume 54 | Number 1 | July 2008 | Pages 182-185
Technical Paper | Tritium Measurement | doi.org/10.13182/FST08-A1791
Articles are hosted by Taylor and Francis Online.
A twin type thermal conduction calorimeter has been specially designed and constructed for absolute measurement of tritium, and then its performance was examined using two kinds of tritium samples, i.e., ZrNi alloy powders loaded with a given amount of tritium. Total amounts of tritium in the ZrNi alloy powders were previously estimated by a small ionization chamber. Changes in radioactivity of two samples were followed for three years, and it was seen that the activity changes obeys the half-life of 4505 days. The initial tritium amounts estimated by the small ionization chamber agreed well with the extrapolated values from the activity changes evaluated by the calorimeter. Namely, it was suggested that the small ionization chamber is able to be used as a secondary standard of the tritium measuring devices. The -ray-induced X-ray counter was also calibrated for non-destructive measurements of high-level tritium by using the present small ionization chamber.