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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.
E. A. Azizov, V. M. Leonov, A. A. Panasenkov, G. N. Tilinin, P. P. Khvostenko
Fusion Science and Technology | Volume 59 | Number 1 | January 2011 | Pages 180-183
doi.org/10.13182/FST11-A11602
Articles are hosted by Taylor and Francis Online.
This paper presents the main parameters and design of proposed T-15MD tokamak. The installation is meant for demonstration of the tokamak two-component operating mode and for steady state operation problems-solving with a plasma current drive (CD) at a level of about 1 MA. Injection of hydrogen neutral beams with a power up to 8 MW is chosen as the main method for noninductive CD. For an electron temperature increase it is supposed to use ECH power up to 6 MW at a frequency of 110 GHz. Parameters of an ion source IVIS KS with a power of 3 MW which is under development for the T-15MD and the main characteristics of the NB injectors are described. Results of preliminary calculations of the tokamak plasma parameters are presented.