Quantitative prediction of rare earth concentrations in salt matrices using laser-induced breakdown spectroscopy for application to molten salt reactors and pyroprocessing
Gregory Hull, Hugues Lambert, Kiran Haroon, Paul Coffey, Timothy Kerry, Edward D. McNaghten, Clint A. Sharrad, Philip A. Martin
Abstract
Pyroprocessing of spent nuclear fuels is an electrochemical separation method where spent metallic fuel is dissolved in a molten salt bath to allow uranium (U) and plutonium (Pu) to be isolated from fission products (FPs) and other impurities.
Topics & Concepts
Molten saltPlutoniumUraniumFission productsSalt (chemistry)ImpuritySpent nuclear fuelMetalElectrochemistryMetallurgyMaterials scienceActinideRadiochemistryNuclear engineeringChemistryInorganic chemistryNuclear chemistryElectrodeEngineeringPhysical chemistryOrganic chemistryLaser-induced spectroscopy and plasmaMetallurgical Processes and ThermodynamicsRadioactive element chemistry and processing