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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.
U.Besserer, R.-D.Penzhorn, R.Brandt
Fusion Science and Technology | Volume 41 | Number 3 | May 2002 | Pages 793-796
Hydride and Storage | Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001 | doi.org/10.13182/FST02-A22693
Articles are hosted by Taylor and Francis Online.
The Tritium Storage facility of the Tritium Laboratory Karlsruhe (TLK), was recently upgraded by four additional uranium beds and one containing ZrCo. Now it is possible to compare under very similar conditions the sorption/desorption properties of uranium and those of ZrCo. To test the adequacy of ZrCo for routine, the getter was folly disproportionated repeatedly using either protium, deuterium or tritium. In all cases was it possible to completely restore the original sorption/desorption properties of the getter. In view of the needs of the Storage and Delivery System (SDS) of the ITER-FEAT Tritium Plant, i.e. delivery of T2 90% - D2 10% and pure D2 to generate mixtures of various compositions, the isotope effects during sorption/desorption cycles of H-D and D-T mixtures in ZrCo granules have been investigated. A transportable storage vessel identical to those containing uranium presently used at TLK for the transport of tritium has been designed, build and filled with ZrCo. These beds fit into the highly sensitive calorimeters available at TLK. With these beds the tritium permanently trapped in U and ZrCo can be compared under similar operation conditions.