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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.
Hans-Dieter Falter, Dragoslav Ciric, Andrea Celentano, Christopher M. Ibbott, Michael J. Watson, Masanori Araki, Satoshi Suzuki, Kazuyoshi Sato
Fusion Science and Technology | Volume 29 | Number 4 | July 1996 | Pages 571-583
Technical Paper | Divertor System | doi.org/10.13182/FST96-A30699
Articles are hosted by Taylor and Francis Online.
Two vapotrons from the Joint European Torus (JET) actively cooled divertor design have been fitted by the Japan Atomic Energy Research Institute with unidirectional high-conductivity carbon-fiber-composite tiles and have been tested in the JET Neutral Beam Test Bed. The test section showed excellent uniformity and accepted power densities up to 30 MW/m2 for equilibrium pulses. The surface temperature was 1100°C at 20 MW/m2. One tile detached at a power density of 25 MW/m2. A total of just under 300 pulses at power densities mostly between 20 and 30 MW/m2 have been fired onto the test sections without additional failure. The hydraulic parameters were as follows: water inlet temperature, 15 to 20°C; average water pressure in the component, 0.4 and 0.69 MPa; flow velocity, 6.9 and 7.5 m/s.