Evaluation of UF{sub 6}-to-UO{sub 2} conversion capability at commercial nuclear fuel fabrication facilities.

Ranek, N. L.; Monette, F. A.

doi:10.2172/783638

Cited by 3 publications

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“…Despite the oxide stoichiometry difference, it is basically the same as the "dry" depleted UF6 to depleted U3O8 process described in Module K1; except in this case, the fuel is enriched in U-235, and the typical plant EU throughput quantities (400 to 1,500 MTU/yr) are three to four orders-of-magnitude smaller than those in the existing U.S. plants for converting enrichment plant waste or "tails" UF6 depleted in U-235. The chemical UF6 deconversion function is discussed in an Argonne National Laboratory report (Ranek and Monette 2001) which surveyed the deconversion capabilities of multiple U.S. commercial fuel fabricators. It should be noted that the Westinghouse (WEC) Columbia Fuel Fabrication facility (Westinghouse 2012) still uses a "wet" EUF6 deconversion process.…”

Section: D1-131 Fuel Fabrication Processmentioning

confidence: 99%

Advanced Fuel Cycle Cost Basis Report: Module D1-1: Uranium-based Ceramic LWR Fuel Fabrication (Rev.2)

Williams,

Hansen,

Hoffman

2023

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Section: D1-131 Fuel Fabrication Processmentioning

confidence: 99%

Advanced Fuel Cycle Cost Basis Report: Module D1-1: Uranium-based Ceramic LWR Fuel Fabrication (Rev.2)

Williams,

Hansen,

Hoffman

2023

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Uranium, Uranium Alloys, and Uranium Compounds

Peehs

Walter²,

Walter

et al. 2007

Ullmann's Encyclopedia of Industrial Chemistry

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The article contains sections titled: 1. Introduction 2. History 3. Physical Properties 3.1. Radioactivity 3.2. Modifications 3.3. Mechanical Properties 3.4. Thermal Properties 3.5. Electrical and Electrochemical Properties 3.6. Magnetic Properties 4. Chemical Properties 5. Occurrence, Requirement, and Production Figures 5.1. Occurrence 5.2. Resources, Requirement, and Production Figures 6. Production 6.1. Uses of Uranium and Uranium Compounds 6.2. From Ore to End Product‐A Review of Processes 6.2.1. From Crude Ore to Yellow Cake 6.2.2. From Yellow Cake to UF 6 6.2.3. From UF 6 to the Nuclear Fuel UO 2 6.3. Detailed Description of the Processes 6.3.1. Digestion and Leaching of Ores 6.3.1.1. Acidic Ores 6.3.1.2. Alkaline Ores 6.3.1.3. Digestion of Phosphate Rock 6.3.2. Treatment of the Liquor 6.3.2.1. Uranium Recovery by Ion Exchange 6.3.2.2. Uranium Recovery by Solvent Extraction 6.3.2.3. Eluex Process 6.3.3. Production of Uranium Ore Concentrate 6.3.3.1. From Precipitation to Yellow Cake Production 6.3.3.2. Processing of Phosphate Liquor and Precipitation of AUC 6.3.4. Final Purification of Uranium Concentrate 6.3.4.1. Dissolution of Yellow Cake 6.3.4.2. Extractive Purification 6.3.5. Production of UO 3 and UO 2 from Purified Uranyl Nitrate Solution 6.3.5.1. Evaporation of Uranyl Nitrate Solution and Denitration by Thermal Decomposition 6.3.5.2. Precipitation of Uranium by the ADU and AUC Processes 6.3.5.3. Reduction of Precipitated Product to UO 2 Powder 6.3.6. Production of UF 4 6.3.6.1. Hydrofluorination of UO 2 6.3.6.2. Hydration and Hydrofluorination of UO 3 6.3.7. Production of UF 6 from UF 4 6.3.7.1. Process Description 6.3.7.2. Chemical Reactors 6.3.7.3. Removal of Excess Fluorine from UF 6 6.3.8. Complete Plant for Production of UF 6 from Uranyl Nitrate 6.3.8.1. French Process in Pierrelatte 6.3.8.2. Allied Chemical Process 6.3.9. Enrichment of 235 U 6.3.9.1. Diffusion Process 6.3.9.2. Ultracentrifuges 6.3.9.3. Nozzle Process 6.3.9.4. Chemical Enrichment 6.3.9.5. Laser Separation Process 6.3.9.6. Plasma Processes 6.3.10. Production of UO 2 Pellets from UF 6 6.3.10.1. Conversion of UF 6 to UO 2 6.3.10.2. Possible Future Developments in the Conversion of UF 6 to UO 2 Powder 6.3.10.3. Pelletizing of UO 2 Powder 6.3.11. Production of Uranium Metal 6.3.11.1. Reduction of UF 6 to UF 4 6.3.11.2. Reduction of UF 4 to Uranium Metal 6.3.11.3. Production of Uranium Powder 7. Uranium Alloys 7.1. Classification 7.2. Production of Important Alloys 8. Uranium Compounds 8.1. Halides 8.1.1. Trivalent Halides 8.1.2. Uranium Tetrahalides 8.1.3. Uranium Pentafluoride 8.1.4. Uranium Hexafluoride 8.2. Carbides 8.3. Nitrides 8.4. Oxides 8.4.1. Uranium Dioxide 8.4.2. Uranium Trioxide 8.4.3. Triuranium Octaoxide 8.4.4. Peroxides 8.5. Nitrates, Sulfates, and the Carbonato Complex 8.5.1. Nitrates 8.5.2. Sulfates 8.5.3. Tricarbonatodioxouranate 9. Safety 9.1. Radiation Shielding 9.2. Safety Against Uncontrolled Criticality 9.3. Geometrically Safe Vessels 9.4. Apparatus with Heterogeneous Neutron Absorbers

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Identification and Elemental Impurity Analysis of Heterogeneous Morphologies in Uranium Oxides Synthesized from Uranyl Fluoride Precursors

et al. 2023

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The surface morphology characteristics of postenrichment deconversion products in the nuclear fuel cycle are important for producing nuclear fuel pellets. They also provide the first opportunity for a microstructural signature after conversion to gaseous uranium hexafluoride (UF 6 ). This work synthesizes uranium oxides from uranyl fluoride (UO 2 F 2 ) starting solutions by the wet ammonium diuranate route and a modification of the dry route. Products are reduced under a nitrogen/hydrogen atmosphere, with and without water vapor in the reducing environment. The crystal structures of the starting materials and resulting uranium oxides are characterized by powder X-ray diffraction. Scanning electron microscopy (SEM) and focused ion beam SEM with energy-dispersive X-ray spectroscopy (EDX) are used to investigate microstructural properties and quantify fluorine impurity concentrations. Heterogeneous distributions of fluorine with unique morphology characteristics were identified by backscatter electron imaging and EDX; these regions had elevated concentrations of fluorine impurities relating to the incomplete reduction of UO 2 F 2 to UO 2 and may provide a novel nuclear forensics morphology signature for nuclear fuel and U metal precursors.

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Evaluation of UF{sub 6}-to-UO{sub 2} conversion capability at commercial nuclear fuel fabrication facilities.

Cited by 3 publications

References 0 publications

Advanced Fuel Cycle Cost Basis Report: Module D1-1: Uranium-based Ceramic LWR Fuel Fabrication (Rev.2)

Advanced Fuel Cycle Cost Basis Report: Module D1-1: Uranium-based Ceramic LWR Fuel Fabrication (Rev.2)

Uranium, Uranium Alloys, and Uranium Compounds

Identification and Elemental Impurity Analysis of Heterogeneous Morphologies in Uranium Oxides Synthesized from Uranyl Fluoride Precursors

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