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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.
W. K. Dagenhart, W. L. Gardner, W. L. Stirling, J. H. Whealton
Fusion Science and Technology | Volume 4 | Number 2 | September 1983 | Pages 1430-1435
Magnet Engineering | doi.org/10.13182/FST83-A23057
Articles are hosted by Taylor and Francis Online.
Scaling studies for a SITEX negative ion source to produce 200-keV, 10-A, long pulse D-beams are under way at Oak Ridge National Laboratory (ORNL). Designs have been restricted to the use of established techniques and reasonably welldemonstrated scaling. The results show that the 1-A SITEX source can be directly scaled to produce 200-keV, 10-A long pulse ion beams with a source power efficiency of <5 kW of total plasma generator power per ampere of D- beam generated. Extracted electron-to-D- ratios should be <0.06, with all extracted electrons recovered at <10% of the first gap potential energy difference. The close-coupled accelerating structure will be 5 em long and have five electrodes with 21 slits each, with a 50-kV/cm field in each gap. No decel electrode was included because of the transverse magnetic field. Electrons formed in each gap by the ~16% charge-exchange loss of D- in the total accelerator column will be collected by electron recovery structures associated with the gaps at an average energy of 50% of a gap's potential energy difference. Atomic gas efficiency will be >67%. Beam divergence calculations using the ORNL optics code give θrms = ±0.4°. The ion source magnetic field provides momentum dispersion of the extracted beam, separating out both the electrons and all heavy ion impurities and low energy D0 particles formed by charge exchange in the accelerating column. A D2 gas neutralization cell and a charge separation magnet provide 1 MW of D0 beam at 200 keV for injection. The overall beam line dimensions are 2.2 × 1.0 × 5.0 m (H × W × L).