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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.
M. Gasparotto et al.
Fusion Science and Technology | Volume 47 | Number 3 | April 2005 | Pages 339-344
Technical Paper | Fusion Energy - Experimental Devices and Advanced Designs | doi.org/10.13182/FST05-A714
Articles are hosted by Taylor and Francis Online.
The WENDELSTEIN 7-X stellarator (W7-X) is the next step device in the stellarator line of IPP and is presently under construction at the Greifswald branch institute. The experiment aims at demonstrating the steady state capability of a stellarator machine at reactor relevant parameters. An important feature of W7-X is the high geometrical accuracy of the magnetic configuration which implies tight tolerances in the construction and assembly phases. The magnetic system consists of 50 non planar and 20 planar superconducting coils. Critical components are the coil support elements connecting the coil to the central mechanical structure and the inter-coil elements connecting the coils one to the other. Efficient thermal insulation of the superconducting coils is achieved by high vacuum and multi-layer insulation. The plasma vessel is composed of 10 half-modules welded together during the assembly phase. A 10 MW ECRH system with CW-capability operation at 140 GHz is required to meet the scientific objective of W7-X.The paper will report the recent progress on W7-X with particular emphasis on the components where high technology solutions have been applied.