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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.
Tadaaki Arita, Toshihiko Yamanishi, Yasunori Iwai, Masataka Nishi, Ichiro Yamamoto
Fusion Science and Technology | Volume 41 | Number 3 | May 2002 | Pages 1116-1120
Isotope Separation | Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001 | doi.org/10.13182/FST02-A22757
Articles are hosted by Taylor and Francis Online.
The separation factors of a cryogenic-wall thermal diffusion column have been measured with H-D and H-T systems. The column was 1.5 m in height and 0.03 m in diameter. Two types of heaters were tested: a tungsten wire 0.5 mm in diameter and a stainless steel sheath heater 11 mm in diameter. The maximum separation factors using the tungsten wire were 49 for an H-D system and 284 for an H-T system under the total reflux mode at 1273 K. At the feed flow rate of 10 cm3/min, the separation factor using the tungsten wire was 55 for the H-T system at 1273 K. The separation factor was decreased as the diameter of the heater was decreased; and the optimum pressure was increased with the diameter of the heater. In the case where the sheath heater (11 mm) was used at 10 cm3/min with the H-T system, the maximum separation factor reached 2660 even at 763 K.