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2024 ANS Annual Conference
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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.
Toshiaki Matsuo, Takuma Yoshida
Nuclear Technology | Volume 136 | Number 3 | December 2001 | Pages 354-366
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT01-A3251
Articles are hosted by Taylor and Francis Online.
This study, which develops a safety assessment code for radioactive waste disposal, consists of two-dimensional analyses of underground water infiltrated flow and near-field radionuclide migration, one-dimensional analyses of far-field migration, and the dose equivalent. The study takes into account the influence of a finite absorption amount of radionuclides in an engineered barrier system (EBS).The safety assessment code is applied to 14C migration calculations. The near-field cylindrical model consists of an equally mixed region of wasteforms and backfill, bentonite, and rock. Carbon-14 coexists with 3.1 × 106 times as much 12C in the wasteforms. The distribution coefficient, maximum absorption amount, and solubility of CO32- against the equally mixed region are assumed to be 2.0 m3/kg, 3.06 mol/kg, and 544 mol/m3, respectively. Then, the release rate from the wasteforms (10-4 to 10-6/yr) and underground water detachment period from the wasteforms are examined to lower the dose equivalent by the intake of well water.The 14C concentration on the EBS boundary is 20 times as large in the case of EBS finite absorption as in the case of infinite absorption. So, the EBS finite absorption leads to absorption saturation and accelerated release of the radionuclides. The influence of the absorption saturation could not be prevented by lowering the release rate. A 3 × 104/yr detachment lowered the dose equivalent to 1/40 of the original case.