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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.
C. J. Martin, L. A. El-Guebaly
Fusion Science and Technology | Volume 52 | Number 4 | November 2007 | Pages 985-989
Technical Paper | Tritium, Safety, and Environment | doi.org/10.13182/FST07-A1622
Articles are hosted by Taylor and Francis Online.
Loss of Coolant Accident (LOCA) and Loss of Flow Accident (LOFA) thermal simulations have been performed for the ARIES compact stellarator fusion power plant. The ARIES-CS design uses three separate coolant loops: lithium-lead (LiPb) in the blanket, helium in the blanket and the shield, and water in the vacuum vessel. The thermal response to LOCA/LOFA conditions was simulated using transient axisymmetric finite element models. In these analyses, the plasma was quenched three seconds after coolant loss, and the temperature of the chamber components subsequently increased due to the generated decay heat. Thermal simulations determined the maximum temperatures reached in the various components were below the 740°C temperature limit for the reusability of the ferritic steel structure.