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Meeting 2025 TMS Annual Meeting & Exhibition
Symposium Special Topics in Nuclear Materials: Lessons Learned; Non-Energy Systems; and Coupled Extremes
Presentation Title Modeling Galvanic Drawdown Separations Technique
Author(s) Garrett Thomas Kemmerly
On-Site Speaker (Planned) Garrett Thomas Kemmerly
Abstract Scope One of the major issues with the nuclear power industry is the build-up of spent nuclear fuel. To combat this issue, many spent nuclear fuel reprocessing concepts have been proposed. This work seeks to develop a preliminary model of a galvanic drawdown cell for a two-step nuclear fuel separation technique. This model is meant to show controlled separation of pure uranium and a plutonium-uranium mixture and simulate the factors that contribute to the proportions of each of these products that are produced. The Nernst equation, Fick’s Law, and mass balance equation are used with a quasi-equilibrium assumption to generate the equations of the model. Some values were derived empirically from experimental data from Dr. Simpson’s group at the University of Utah. Based on the results, the model has been shown to accurately predict the most significant parameters determining the materials separated over time and shows predictive capabilities for simple geometries.
Proceedings Inclusion? Planned:
Keywords Nuclear Materials, Recycling and Secondary Recovery, Electrometallurgy

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

Advancing Radioisotope Heat Sources: Enhancing RPS for Extreme Environments
Atomistic Simulation of Thermal and Irradiation Creep Mechanisms in BCC-Fe and FCC-Ni using Defect Rate-Based Long-time Dynamics
Best Practices for Irradiation Experiment Design For Nuclear Fuels and Materials Research
Cavity Formation Induced by Swift Heavy Ion Irradiation in AlN/GaN
Comparison of Hardening and Microstructures of Structural Alloys Irradiated with Fast Neutrons and Dual Ions
Developing a High-Performance Cluster Dynamics Code: Challenges and Lessons Learned
Effect of Applied Stress on Radiation-Induced Loop and Raft Formation in a BCC Metal
Effect of Tensile Stress Gradients on the Multi-Length-Scale Microstructure in Thermal and Irradiation Creep of 316L Stainless Steel
Energy Dispersive X-Ray Spectroscopy (EDS) Induced Defects and Implantation Induced Impurities in Uranium Nitride (UN) and SIMFUEL Pellets
Fabrication of Titanium-Containing Tri-Carbide Ultra-High Temperature Ceramics
GIRAFFE – In Situ Material TestsUnder Fusion-Relevant Conditions
In-situ Electron Microscopy Characterization of Deformation Mechanisms of Inconel 718 Irradiated with Simultaneous High Energy Protons and Spallation Neutrons
Influence of Radiation Swelling on Residual Stresses and Measurement of Micromechanical Properties
Materials Research for High-Power Accelerator Beam-Intercepting Devices
Modeling Galvanic Drawdown Separations Technique
Phase Field Modeling of Irradiation-Induced Amorphous-to-Crystalline (A-C) Transformations in Structural Ceramics
Post Irradiation Examination and Administrative Lifetime Limits of Highly Irradiated Components at The Spallation Neutron Source
Small Scale Tests, Big Lessons Learned
The Recovery of Irradiation Damage for Zircaloy-2 and Zircaloy-4 following Irradiation at Higher Temperatures of 377-410°C

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