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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.
Kenjiro Matsuhiro, Hirofumi Nakamura, Takumi Hayashi, Hiroo Nakamura, Masayoshi Sugimoto
Fusion Science and Technology | Volume 48 | Number 1 | July-August 2005 | Pages 625-628
Technical Paper | Tritium Science and Technology - Materials Interaction and Permeation | doi.org/10.13182/FST05-A1003
Articles are hosted by Taylor and Francis Online.
In International Fusion Material Irradiation Facility (IFMIF), neutrons are produced by the reaction between 40 MeV deuterium and liquid lithium. In this process, tritium (3 × 1011 Bq/h) is generated in the lithium flow. Tritium permeation and inventory of IFMIF lithium loop components are evaluated for safety of the IFMIF and the design of tritium processing system of the IFMIF. The tritium permeation rate from a V-Ti hot trap is about 95% of the total amount, 1.0 × 106 Bq/h, from lithium loop. Therefore, the reduction of the tritium permeation rate from only the V-Ti hot trap can directly reduce the total tritium permeation from the Li loop and the gaseous tritium in the Li loop area. Total tritium contained in the walls ewt by liquid lithium in the IFMIF is 5.3 × 107 Bq, which is much smaller than 4.9 × 1014 Bq of tritium contained in the Li flow with a volume of 9 m3.