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Return of the HB Line at SRS
The Department of Energy is bringing the HB Line facility at the Savannah River Site back on line to recycle surplus plutonium and produce uranium-plutonium mixed oxide (MOX) fuel for advanced reactors.
Restarting the facility will be a multiyear process and will yield opportunities for increased domestic production of isotopes with scientific and commercial value. The DOE said that once operational, the HB Line will accelerate the Office of Environmental Management’s plutonium disposition mission by 10 to 13 years while reducing the existing cost.
Fumito Okino, Kazuyuki Noborio, Ryuta Kasada, Satoshi Konishi
Fusion Science and Technology | Volume 64 | Number 3 | September 2013 | Pages 549-551
Fusion Technologies: Heating and Fueling | Proceedings of the Twentieth Topical Meeting on the Technology of Fusion Energy (TOFE-2012) (Part 2) Nashville, Tennessee, August 27-31, 2012 | doi.org/10.13182/FST13-A19151
Articles are hosted by Taylor and Francis Online.
The feasibility of deuterium mass transport prediction from falling droplets of Pb-17Li was verified. This prediction is one of key techniques of the engineering design of tritium extraction device for the fusion reactor. The mass-transfer-coefficient, deduced on the surface-stretch-model was applied. As the experimental results, deuterium mass transport in the falling droplets from four different size nozzles, at four temperature conditions between 375 °C and 450 °C, performed by the authors, were compared. Resultant Sherwood number was between 494 and 598, and explained the experimental result of the two orders of magnitudes differences with the reported diffusion in static condition. Though, the ratio of theory and experiment still remained between 1.8 and 2.3. Simple boundary condition, not considering the number of oscillation, wide range of reported diffusivity value are considered to be main reasons of the deviation. The analysis model including these factors is to improve prediction accuracy. This result is expected to contribute to a preliminary design of a tritium extraction device.