Advanced Separation Techniques for Nuclear Fuel Reprocessing and Radioactive Waste Treatment

Professor Kenneth L. Nash of Washington State University is an expert in the fields of nuclear separation processes and the nuclear fuel cycle. Dr Gregg J. Lumetta of Pacific Northwest National Laboratory is an expert in the fields of nuclear separation processes and the nuclear fuel cycle.

• Contributor contact detailsWoodhead Publishing Series in EnergyPrefacePart I: Fundamentals of radioactive materials separations processes: chemistry, engineering and safeguardsChapter 1: Chemistry of radioactive materials in the nuclear fuel cycleAbstract:1.1 Introduction1.2 Chemical features of important fission products and actinides1.3 Relevant actinide chemistry in the nuclear fuel cycle1.4 Essential features of solvent extraction separations in the nuclear fuel cycle1.5 Behavior in molten salts/molten metals/ionic liquids/alternative media1.6 Interactions at interfaces significant to the nuclear fuel cycle1.7 Future trendsChapter 2: Physical and chemical properties of actinides in nuclear fuel reprocessingAbstract:2.1 Introduction2.2 Thermodynamic properties of compounds2.3 Speciation, complexation and reactivity in solution of actinides2.4 Irradiation effects2.5 Future trends2.6 Sources of further information and adviceChapter 3: Chemical engineering for advanced aqueous radioactive materials separationsAbstract:3.1 Introduction3.2 Containment concepts3.3 Separations equipment3.4 Equipment materials considerations3.5 Future trends3.6 Sources of further information and adviceChapter 4: Spectroscopic on-line monitoring for process control and safeguarding of radiochemical streams in nuclear fuel reprocessing facilitiesAbstract:4.1 Introduction4.2 Static spectroscopic measurements4.3 Demonstration of spectroscopic methods4.4 Conclusions4.5 Acknowledgments4.7 Appendix: acronymsChapter 5: Safeguards technology for radioactive materials processing and nuclear fuel reprocessing facilitiesAbstract:5.1 Introduction5.2 Requirements5.3 Safeguards technology5.4 Safeguards applications for aqueous separations5.5 Safeguards applications for pyrochemical separations5.6 AcknowledgementPart II: Separation and extraction processes for nuclear fuel reprocessing and radioactive waste treatmentChapter 6: Standard and advanced separation: PUREX processes for nuclear fuel reprocessingAbstract:6.1 Introduction6.2 Process chemistry6.3 Current industrial application of PUREX6.4 Future industrial uses of PUREX6.5 ConclusionsChapter 7: Alternative separation and extraction: UREX+ processes for actinide and targeted fission product recoveryAbstract:7.1 Introduction7.2 Separation strategy7.3 UREX + LWR SNF GNEP application: separation strategy7.4 Benefits of using models to design flowsheets7.5 Advantages and disadvantages of techniques7.6 Future trendsChapter 8: Advanced reprocessing for fission product separation and extractionAbstract:8.1 Introduction8.2 Separation methods, advantages/disadvantages, and future trends8.3 Conclusions and future trendsChapter 9: Combined processes for high level radioactive waste separations: UNEX and other extraction processesAbstract:9.1 Introduction to universal extraction process (UNEX) and other processes9.2 Universal processes for recovery of long-lived radionuclides9.3 Development and testing of the universal extraction (UNEX) process and its modifications9.4 ConclusionsPart III: Emerging and innovative techniques in nuclear fuel reprocessing and radioactive waste treatmentChapter 10: Nuclear engineering for pyrochemical treatment of spent nuclear fuelsAbstract:10.1 Introduction10.2 Process chemistry and flowsheet of pyrochemical processing10.3 Design and installation of process equipment10.4 Materials behaviour and interactions10.5 Developments in monitoring and control for pyrochemical processing10.6 Techniques for safe and effective interoperation of equipment10.7 Future trends10.8 Sources of further information and adviceChapter 11: Development of highly selective compounds for solvent extraction processes: partitioning and transmutation of long-lived radionuclides from spent nuclear fuelsAbstract:11.1 Introduction11.2 Which long-lived radionuclides to partition and why?11.3 How to develop selective ligands and extractants?11.4 Examples of development of highly selective compounds in European partitioning and transmutation (P&T) strategy11.5 Future trends11.6 Conclusions11.7 Sources of further information and advice11.8 AcknowledgmentChapter 12: Developments in the partitioning and transmutation of radioactive wasteAbstract:12.1 Introduction to transmutation12.2 Modelling transmutation processes and effects12.3 Systems for transmutation: design and safety12.4 Transmutation fuel development12.5 Future trendsChapter 13: Solid-phase extraction technology for actinide and lanthanide separations in nuclear fuel reprocessingAbstract:13.1 Introduction13.2 Basic methodology of solid-phase extraction13.3 Solid-phase extraction sorbents for actinides and lanthnides13.4 Modeling of solid-phase extraction systems13.5 Advantages and disadvantages of solid-phase extraction in treatment processes for nuclear fuel reprocessing streams13.6 Future trends in solid-phase extraction technology for nuclear fuel reprocessing applications13.7 Sources of further information and advice13.8 AcknowledgmentChapter 14: Emerging separation techniques: supercritical fluid and ionic liquid extraction techniques for nuclear fuel reprocessing and radioactive waste treatmentAbstract:14.1 Introduction14.2 Supercritical fluid extraction of lanthanides and actinides14.3 Direct dissolution of uranium oxides in supercritical carbon dioxide14.4 Current industrial demonstrations of supercritical fluid extraction technology for nuclear waste treatment and for reprocessing spent fuel14.5 Ionic liquid and supercritical fluid coupled extraction of lanthanides and actinides14.6 Future trendsChapter 15: Development of biological treatment processes for the separation and recovery of radioactive wastesAbstract:15.1 Introduction15.2 Classification of waste15.3 Waste from high temperature fast reactors15.4 Treatment options15.5 Biological removal of metal oxyions15.6 Biosorption and recovery15.7 Biofilm processes15.8 Future trends15.11 Engineering dimensions (units)Index