Conference Logo ProgramMaster Logo
Conference Tools for MS&T25: Materials Science & Technology
Login
Register as a New User
Help
Submit An Abstract
Propose A Symposium
Presenter/Author Tools
Organizer/Editor Tools

About this Abstract

Meeting MS&T25: Materials Science & Technology
Symposium Advancements in Molten Salt/Metal Technology in Energy Applications: From Atoms to Plants
Presentation Title Separation of fission products from high-level waste salt via melt-crystallization
Author(s) Rocio Rodriguez Laguna, Tae-Sic Yoo, Kevin R Tolman, Brian S Newell, Jacob A Yingling, Morgan T Kropp, Stephanie Castro Baldivieso
On-Site Speaker (Planned) Rocio Rodriguez Laguna
Abstract Scope Spent nuclear fuel contains both fissile material and fission by-products. Reprocessing techniques, such as pyroprocessing, enable the recovery of fissile materials for further use, while leaving the fission products in the pyroprocessing salt for disposal. This process generates a considerable volume of high-level waste. This study aims to use a melt-crystallization technique to separate fission products from pyroprocessing salt to reduce the volume, heat load, and radiotoxicity of nuclear waste. Among the challenging fission products, cesium-137 (Cs-137) stands out as a significant contributor to the radiotoxicity and decay heat of high-level nuclear waste. A dual-heater setup was successfully employed to separate cesium from both chloride-based pyroprocessing salts and fluoride-based salts. These types of salts are relevant to advanced nuclear fuel cycles, including molten salt reactors. The findings demonstrate that melt-crystallization is a suitable technique for nuclear waste management, potentially reducing the burden on long-term storage repositories.

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

A Computational Approach to Investigate the Role of Impurities on Corrosion Behavior in Molten Salt Reactors
Accurate Free Energy Simulations in Molten Salts with Machine Learning Potentials and High-Level Quantum Chemical Methods
Beyond proof of concept: the role of lab scale pilots in parallel to commercial operations
Development of a Thermal Conductivity Model for Molten Salts Based on the Pair Distribution Function
Electrochemical behavior of oxygen-evolving precious metal anodes in molten LiCl-Li2O electrolyte
EuCl3 mediated corrosion of Ni and Ni-20Cr Model Alloy in LiCl-KCl molten salt
Experimental calorimetry of heat capacity and mixing enthalpy of molten chloride salts
Fuel Salt Synthesis for the Molten Chloride Reactor Experiment: Scale-up, Operations, and Production Update
Laser-Spectroscopy Testbed for Impurity Monitoring in High-Temperature Reactors
Molten Salt Properties Capabilities at ORNL
Novel Al/Ti-Modified Ni-Mo-W-Cr Alloys for High Temperature Structural Applications in Molten Chloride Fast Reactors
Radiation-induced iodine chemistry in high-temperature molten salts
Separation of fission products from high-level waste salt via melt-crystallization
Synchrotron-Based X-ray Spectroscopy of Molten Salts
Testing Reference Electrodes in FLiNaZr Molten Salt
The Effect of Irradiation on the Densities of Chloride-Bearing Molten Salts
Towards the development of an inert anode for reprocessing of used nuclear fuel

Questions about ProgramMaster? Contact programming@programmaster.org