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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.
Tristan S. Hunnewell, Kyle L. Walton, Sangita Sharma, Tushar K. Ghosh, Robert V. Tompson, Dabir S. Viswanath, Sudarshan K. Loyalka
Nuclear Technology | Volume 198 | Number 3 | June 2017 | Pages 293-305
Technical Paper | doi.org/10.1080/00295450.2017.1311120
Articles are hosted by Taylor and Francis Online.
Type 316L stainless steel (SS 316L) is a candidate material for the reactor core barrel and selected internal components for high (and very high) temperature gas reactors. An apparatus constructed in accordance with the standard ASTM C835-06 was used for measuring total hemispherical emissivity of this material for the following surface conditions: (1) “as-received” from the manufacturer, (2) sandblasted with alumina beads, (3) sandblasted and coated with IG-11 nuclear-grade graphite powder, and (4) oxidized in air at 973 K for different durations. The emissivity of the as-received samples increased from 0.25 at 436 K to 0.36 at 1166 K. Sandblasting with 60-grit–sized alumina beads increased the emissivity from 0.32 to 0.44 in the temperature range from 561 to 1095 K. The emissivity continued to increase with sandblasting with 120- and 220-grit alumina beads, despite decrease in surface area associated with the more finely sized alumina beads. The coating of IG-11 graphite powder further increased the emissivity of the sandblasted surfaces. Following a similar trend, the IG-11–coated surfaces sandblasted by 120- and 220-grit alumina had an emissivity from 0.42 at 540 K to 0.57 at 1075 K. Electron micrographs showed more deposition of IG-11 powder on the 120- and 220-grit sandblasted surfaces. Oxidation in air at 973 K for 5 min also increased the emissivity of SS 316 L. Oxidations for 10 and 15 min provided an additional increase, but it was not as significant. Analysis indicates that spallation of oxide layer occurred between 10 and 15 min oxidation. This is consistent with studies on the time variation of total normal emissivity of SS 316L for oxidation at similar temperature.