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2024 ANS Annual Conference
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Las Vegas, NV|Mandalay Bay Resort and Casino
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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.
Wei Shen, Dimitar Altiparmakov
Nuclear Science and Engineering | Volume 174 | Number 2 | June 2013 | Pages 109-134
Technical Paper | doi.org/10.13182/NSE12-42
Articles are hosted by Taylor and Francis Online.
This paper presents a multicell correction method that has been developed and implemented in the code suite WIMS-AECL/RFSP to capture the effects of the lattice-cell neighborhood while maintaining the basic structure of the single-cell-based reactor-physics methodology traditionally used for Canada Deuterium Uranium (CANDU)-reactor calculations for decades. To validate the effectiveness in treating the core-reflector interface heterogeneity as well as the checkerboard-voiding scenario, the results of WIMS-AECL/RFSP calculations (with and without the multicell correction) are compared with the results of MCNP5 full-core calculations for CANDU-type reactors. The presented results show that the multicell correction method is effective, generic, and capable of capturing the heterogeneity effects of the neighborhood in CANDU-type reactors.