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Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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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.
Mark S. Lanza (Framatome Inc.), Donald R. Todd (PNNL)
Proceedings | Advances in Thermal Hydraulics 2018 | Orlando, FL, November 11-15, 2018 | Pages 27-32
A general based charcoal filter model was added to the thermal hydraulics code GOTHIC Version 8.2. The model can be used to simulate unsteady iodide transport and adsorption within a charcoal filter that is used to filter vapor exiting the containment of a nuclear plant. The code accepts user inputs for adjusting filtering efficiency and performs calculations for the time and space dependent concentration of iodides in the vapor phase as well as the adsorbed phase within a charcoal filter.
The model includes advective and diffusive transport for iodides coupled with a sorption kinetics model, including first-order reversible physisorption and second-order irreversible chemisorption. Multiple independent gaseous compounds can be modeled simultaneously. The iodide compounds within these gasses are coupled by a decay-chain model and the combined concentration of the gaseous compounds is coupled to the chemisorption capacity of the filter.
Validation of the model to predict iodide transport and sorption within impregnated, activated charcoal was performed through experimental benchmarking. The validation demonstrates that the numerical solution correctly predicts measured data.