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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.
V. Widak, P. Norajitra, J. Reiser
Fusion Science and Technology | Volume 56 | Number 2 | August 2009 | Pages 1028-1032
Divertors and High Heat Flux Components | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 2) | doi.org/10.13182/FST09-A9046
Articles are hosted by Taylor and Francis Online.
Within the EU power plant conceptual study (PPCS), a modular He-cooled divertor concept (Ref. 1) has been investigated at the Forschungszentrum Karlsruhe to achieve a heat flux of at least 10 MW/m2. The divertor conceptual design is based on the use of a tile made of tungsten, a structural element made of tungsten alloy, and a steel cartridge. The cooling of the divertor module is realized by an impingement of helium jets (10 MPa, 600 °C) flowing through an array of small jet holes located at the top of the cartridge, able to remove the high heat flux incident on the top surface of the tiles.In this paper a modular design of a helium cooled divertor is introduced. A method of design examination regarding the cooling capability and the component stresses are pointed out. The method is based on the use of a combined system of modern computer tools. For the 3D design construction, the CAD program CATIA V5 was utilized. The simulation calculations were performed in two steps: thermo-hydraulic CFD calculations using the ANSYS CFX tool and thermo-mechanical FEM calculations with the ANSYS code. The CFD computations were done taking into account the design geometry with an appropriate meshing and the boundary conditions, i.e. the defined heat flux, the helium pressure and temperature at the inlet. Among other things, the heat-transfer-coefficients received from the CFD runs were then used for the following FEM analyses. The simulation results and a potential of design improvement will be discussed.