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Symposium LL, 'Scientific Basis for Nuclear Waste Management XXXVI', was held November 25-30 at the 2012 MRS Fall Meeting in Boston, Massachusetts. This Symposium continues to set the research agenda in the field of radioactive waste management, charting the development of waste processing, conditioning, packaging and disposal. Symposium XXXVI featured 77 presentations, delivered over four days during the 2012 MRS Fall Meeting, from participants in Australia, Austria, Finland, France, Japan, Russia, Spain, Sweden, Switzerland, the United Kingdom, and the United States of America. Sessions reported on advances in glass and ceramic wasteforms, conditioning of technetium, management of spent nuclear fuel, and geological disposal, plus a special joint session with Symposium HH, on radiation effects in nuclear materials. Each paper provides a snapshot of the exciting recent developments in each of these areas and the international progress toward achieving the safe, timely and cost-effective management and disposal of radioactive wastes.
Contents
Part I. Glass Wasteforms Ialumino-borosilicate glass for the encapsulation of high temperature reactor (HTR) fuel; 2. Long-term aqueous alteration kinetics of an alpha-doped SON68 borosilicate glass; 3. Corrosion and alteration of lead borate glass in bentonite equilibrated water; 4. Vitrification of high molybdenum feeds in the presence of reprocessing waste liquor; 5. The effect of c-radiation on mechanical properties of model UK nuclear waste glasses; 6. Structural characterization and analysis of glasses in the Al2O3-B2O3-Fe2O3-Na2O-SiO2 system; 7. Infrared and raman spectroscopic study of glasses in the Al2O3-B2O3-Fe2O3-Na2O-SiO2 system; 8. XAFS study of Fe K edge in Al2O3-B2O3-Fe2O3-Na2O-SiO2 glasses; Part II. Ceramic Wasteforms - Beta Decay: 9. Thermal conversion of Cs-exchanged IONSIV IE-911 into a novel caesium ceramic wasteform by hot isostatic pressing; 10. Aging studies of Pu-238 and -239 containing calcium phosphate ceramic waste-forms; 11. Development of the synthetic rock technique for the immobilization of iodine: kinetics of the alumina matrix dissolution under high alkaline conditions; 12. A study on iodine release behavior from iodine-immobilizing cement solid; 13. Towards a silicate matrix for the immobilisation of Halide-rich wastes; 14. Decontamination of molten salt wastes for pyrochemical reprocessing of nuclear fuels; 15. Thermodynamic modeling and experimental tests of irradiated graphite molten salt decontamination; Part III. Technetium Solutions: 16. Ceramic immobilisation options for technetium; 17. Technetium incorporation into C14 and C15 laves intermetallic phases; 18. Technetium-99m transport and immobilisation in porous media: development of a novel nuclear imaging technique; Part IV. Spent Nuclear Fuel: 19. Modelling the activation of H2 on spent fuel surface and inhibiting effect of UO2 dissolution; 20. Corrosion study of SIMFUEL in aerated carbonate solution containing calcium and silicate; 21. Effects of matrix composition on instant release fractions from high burn-up nuclear fuel; 22. Reducing the uncertainty of nuclear fuel dissolution: an investigation of UO2 analogue CeO2; 23. Research and development on cementation of Liquid Radioactive Waste (LRW) resulting from spent nuclear fuel reprocessing in the Experimental Demonstration Center (EDC) of Mountain Chemical Combine; Part V. Waste Repositories: 24. NMR study of interlayer and non-interlayer porewater in water-saturated bentonite and montmorillonite; 25. Long-term corrosion of Zircaloy-4 and Zircaloy-2 by continuous hydrogen measurement under repository condition; 26. Radioelement solubilities in SR-site, the influence of variability and uncertainty; 27. Glass-iron-clay interactions in a radioactive waste geological disposal: a multiscale approach; 28. Suitability of bioapatite as backfill material for nuclear waste isolation; 29. Collocation and integration of back-end fuel cycle facilities with the repository: implications for waste forms; 30. Processing and disposal of radioactive waste: selection of technical solutions; 31. Assessment of the evolution of the redox conditions in the SKB ILW-LLW SFR-1 repository (Sweden); 32. Characterization of radionuclide retaining properties of backfill materials for near surface repositories for low and intermediate level radioactive wastes.
