Documents in the NTIS Technical Reports collection are the results of federally funded research. They are directly submitted to or collected by NTIS from Federal agencies for permanent accessibility to industry, academia and the public.  Before purchasing from NTIS, you may want to check for free access from (1) the issuing organization's website; (2) the U.S. Government Printing Office's Federal Digital System website; (3) the federal government Internet portal; or (4) a web search conducted using a commercial search engine such as
Accession Number DE13-1097006
Title Modeling Solute Thermokinetics in LiCI-KCI Molten Salt for Nuclear Waste Separation, Fuel Cycle R-D.
Publication Date 2013
Media Count 92p
Personal Author D. Morgan
Abstract This project has developed first-principles based molecular modeling and simulation approaches to predict fundamental thermokinetic properties of dissolved actinides and fission products in molten salts. Present nuclear waste separation methods are controlled by solute and salt properties that are difficult and expensive to measure experimentally for the wide range of relevant salt mixtures. The simulation approaches developed in this work can provide essential data from first-principles, thereby reducing the number of required experiments. More broadly, the modeling is of value for interpreting experimental results, guiding new experiments, validating analytical models, and for optimizing waste separation by enabling rapid and inexpensive exploration of new salt configurations and operating conditions. The properties predicted with the modeling are density, which is used to assess the amount of dissolved material in the salt mixtures, diffusion, which can control rates of material transport during separation, and solute activity, which determines total solubility and reduction potentials used during electrorefining. The work has focused on LiCl-KCl salts, which are used for treating spent EBR-II fuel. Studies were performed using LiCl, KCl, and LiClKCl eutectic composition (58 mol% LiCl, 42 mol% KCl) salts. The work focused on La, Sr, and U impurities (defined as solutes in this document), which are chosen to include the important distinct categories of lanthanides, alkali earths, and actinides, respectively.
Keywords Actinides
Fission products
Fuel cycle
Molten salts
Radioactive waste processing
Separation processes

Source Agency Technical Information Center Oak Ridge Tennessee
NTIS Subject Category 77G - Radioactive Wastes & Radioactivity
77I - Reactor Fuels & Fuel Processing
Corporate Author Wisconsin Univ.-Madison.
Document Type Technical report
Title Note N/A
NTIS Issue Number 1412
Contract Number N/A

Science and Technology Highlights

See a sampling of the latest scientific, technical and engineering information from NTIS in the NTIS Technical Reports Newsletter

Acrobat Reader Mobile    Acrobat Reader