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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.
P. Y. Li, C. J. Pan, B. L. Hou, S. L. Han, Z. C. Sun, F. Savary, Y. K. Fu, R. Gallix, N. Mitchell
Fusion Science and Technology | Volume 61 | Number 2 | February 2012 | Pages 141-146
Technical Paper | First Joint ITER-IAEA Technical Meeting on Analysis of ITER Materials and Technologies | doi.org/10.13182/FST12-A13380
Articles are hosted by Taylor and Francis Online.
The research and development of manufacture-related technology for ITER magnet supports is one of the tasks for construction. AISI 316LN austenitic stainless steel has been developed and tested as the main raw material. The material shows excellent mechanical properties at room temperature, 77 K, and 4.2 K. An alternative design for the toroidal field support manufacture without welding was carried out. The structural analysis shows no stress concentration and buckling in the present design during ITER operation. However, further engineering tests of the structural stability under various load combinations are also scheduled. A brazed connection to attach the cooling pipes to the support plates is suggested. Several kinds of candidate brazing fillers, such as Sn-Pb-, Ag-, and Cu-based alloys have been developed. The tensile strength of the brazed solders is up to 400 MPa at 77 K for the Ag-based and Cu-based fillers. For correction coil support, the plasma spray insulation coating was developed and introduced.