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Fusion Science and Technology
Latest News
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.
M. Sawan, L. El-Guebaly, P. Wilson
Fusion Science and Technology | Volume 52 | Number 4 | November 2007 | Pages 763-770
Technical Paper | Nuclear Analysis and Experiments | doi.org/10.13182/FST07-A1582
Articles are hosted by Taylor and Francis Online.
Detailed three-dimensional nuclear analyses have been carried out for the chamber of a power plant concept that utilizes the Z-Pinch driven inertial confinement technology with a target yield of 3 GJ and repetition rate of 0.1 Hz per chamber. The elliptical chamber concept was modeled with the double-layered Recyclable Transmission Lines (RTL). Thick liquid jets are utilized to breed tritium, absorb energy, and shield the chamber wall. Two liquid breeder options were considered; the molten salt Flibe and the LiPb eutectic (Li17Pb83). The chamber wall is made of the low activation ferritic steel alloy F82H. While both breeders have the potential for achieving tritium self-sufficiency, the thermal power is ~6.5% higher with LiPb. However, a 55% thicker jet zone is required with LiPb to provide adequate chamber wall shielding. A thicker chamber wall is required with LiPb to reduce the nuclear energy leakage below 1%. The chamber wall does not need replacement except for the top part around the jet nozzles. Helium production in the chamber wall protected by LiPb is much lower than that with Flibe. Rewelding is possible only in the lower part of chamber wall below the pool.