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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.
Hee Taek Chae, Jong Hark Park, Heonil Kim, Soon Heung Chang
Nuclear Technology | Volume 148 | Number 3 | December 2004 | Pages 287-293
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT04-A3567
Articles are hosted by Taylor and Francis Online.
Critical heat flux (CHF) tests using rod bundles were performed under low-flow conditions to supplement the CHF database for HANARO fuel. The test rod had the same geometric configuration as the HANARO fuel, and its aluminum cladding with fins was made by coextrusion on the stainless steel heating tube. Three types of test sections were used: hexagonal with seven rods, triangular with three rods, and rectangular with four rods. Each test bundle has three spacers axially, and a view window is located in the upper region of the test section. Flow patterns until the CHF condition are typically varied from bubbly flow to annular flow, and then CHF occurs through the long annular flow period. A total of 36 bundle CHF data were obtained from the 3 test sections. The results showed that the CHFs for bundles are larger than those for a single rod with the same geometrical dimension by a maximum 26% as the mass flux changes. It is considered that these results are induced by the enhancement of the turbulence and thermal mixing generated by the spacers. In addition, measurement of the onset of nucleate boiling (ONB) in the rectangular bundle was attempted using sound signals. A hydrophone was attached near the outlet wall of the test section. Hydrophone signals around the ONB point were measured and analyzed based on the frequency through the real fast Fourier transform. Frequency analysis showed clear differences in the power spectral densities for two different frequency ranges before and after ONB, which verifies the usefulness of sound signals for ONB detection.