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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.
Günter Neffe, Eike Hutter, Hank Brunnader
Fusion Science and Technology | Volume 28 | Number 3 | October 1995 | Pages 1365-1370
Design, Operation, and Maintenance of Tritium System | Proceedings of the Fifth Topical Meeting on Tritium Technology In Fission, Fusion, and Isotopic Applications Belgirate, Italy May 28-June 3, 1995 | doi.org/10.13182/FST95-A30602
Articles are hosted by Taylor and Francis Online.
On August 24, 1993, the gas chromatography based Isotopic Separation System (ISS) built in Canada by CFFTP was delivered to the Forschungszentrum in Karlsruhe (FZK) to form part of the Tritium Laboratory Karlsruhe (TLK) infrastructure. The system was successfully reassembled at Karlsruhe, and has been commissioned with a mixture of hydrogen and deuterium. To date, four experimental campaigns have been carried out which show that at liquid nitrogen temperatures, the system is capable of separating 120 I batches of H2, HD and D2. During 1995, the ISS will complete licensing and will be prepared for tritium service.
