HALEU Production in FCF
This is one more version of a PowerPoint presentation that has been given for many years.
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
Engineering topics
Fredrickson, Guy L
Publications and source records attributed to Fredrickson, Guy L.
High Assay Low Enriched Uranium (HALEU) Production at the Fuel Conditioning Facility
Similar versions of this presentation have been used in the past for many years. The presentation describes spent fuel treatment operations in FCF.
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
Nuclear Reactor Energy Balance
This is a presentation for an invited lecture at Montana Tech, Butte, MT. The lecture will be given to a graduate level "Reactor Design Class" in the Metallurgy Department. The lecture does not include any sensitive information.
11 - NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
Overview of Pyroprocessing
This is a PPT presentation on the spent fuel treatment operations in the Fuel Conditioning Facility at MFC.
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
Electrorefiner Speciation and Phase Model for Prediction of Operation Lifetime
The Mk IV electrorefiner (ER) at Idaho National Laboratory has recovered uranium metal from used nuclear fuels for 27 years. Thus, large quantities of fission product chlorides more electropositive than uranium have accumulated in the ER salt, increasing the complexity of phase equilibria and salt speciation. Importantly, the melt temperature of the salt increases with ER operation and will ultimately exceed design limits without intervention. Methods to remove fission products from molten chloride salt are known, but their implementation at scale is not yet demonstrated. In this work, historical ER composition and differential scanning calorimetry (DSC) are utilized to develop coupled speciation and chloride salt solution thermochemistry models, which enable accurate present-day analysis of ER salt as well as forecast its future disposition. The developed thermochemical models are applicable to chloride salts generally and have been made available in the Molten Salt Thermal Properties Database – Thermochemical.
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗