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Fusion Science and Technology
Latest News
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. Rotti, N. Panda, H. Patel, N. Kanoongo, A. Chakraborty, K. Balasubramanian
Fusion Science and Technology | Volume 65 | Number 2 | March-April 2014 | Pages 205-211
Technical Paper | doi.org/10.13182/FST13-669
Articles are hosted by Taylor and Francis Online.
In high heat flux components of neutral beam injector (NBI) systems, CuCrZr alloy is used as a heat sink material. In different national standards, chromium content varies from 0.4 to 1.5 wt%, and zirconium content varies from 0.03 to 0.25 wt%. Indian CuCrZr material was produced at the Non-Ferrous Materials Technology Development Centre and used for the NBI system of the Indian tokomak SST-1, which complied with these chemical composition ranges. The properties of the Indian CuCrZr material were in accordance with procurement specifications. CuCrZr ITER-grade (IG) specifications are as defined in “ITER Materials Properties Handbook” (MPH). The MPH recommends a narrower range of Cr and Zr contents. The reason for limiting the Cr content is that a high Cr content may result in the formation of coarse Cr precipitates, which affect the radiation resistance. Indian CuCrZr with ITER specifications has been produced in a large number (38) of heats and characterized for compositional, tensile, grain size, and weld properties. The properties are, in general, found to comply with those of ITER specifications. The material-processing and component-making steps have been determined, and prototypes of heat transfer elements have been made. Residual ion dump plates have been successfully deep drilled, and component welding trials are in progress. This paper discusses experiences in producing CuCrZr IG and making the elements.