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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.
R. L. Boivin, J. L. Luxon, M. E. Austin, N. H. Brooks, K. H. Burrell, E. J. Doyle, M. E. Fenstermacher, D. S. Gray, M. Groth, C.-L. Hsieh, R. J. Jayakumar, G. R. McKee, C. J. Lasnier, A. W. Leonard, R. A. Moyer, T. L. Rhodes, J. C. Rost, D. L. Rudakov, M. J. Schaffer, E. J. Strait, D. M. Thomas, M. Van Zeeland, J. G. Watkins, G. W. Watson, W. P. West, C. P. C. Wong
Fusion Science and Technology | Volume 48 | Number 2 | October 2005 | Pages 834-851
Technical Paper | DIII-D Tokamak | doi.org/10.13182/FST05-A1043
Articles are hosted by Taylor and Francis Online.
The DIII-D tokamak, located at General Atomics in San Diego, California, has long been recognized as being one of the best diagnosed magnetic fusion experiments. Composed of more than 50 individual systems, the diagnostic set takes advantage of a high number of large-aperture access ports. These instruments are used in support of basic control of the tokamak and experiments in the transport, stability, boundary and heating, and current drive science areas. These systems have contributed to the success of the Advanced Tokamak program, in addition to the many contributions to our physics understanding and real-time control of fusion-relevant plasmas. Numerous novel techniques have been developed, tested, and fielded on DIII-D including new approaches required for a burning plasma experiment. Details of the diagnostic systems will be described along with some illustrative recent results.
