Table of Contents

Part I. Capture and Immobilization of Radionuclides: 1. Current status of immobilization techniques for geological disposal of radioactive iodine in Japan; 2. French studies on the development of potential conditioning matrices for iodine 129; 3. Effects of hydrosulfide and pH on iodine release from an alumina matrix solid confining silver iodide; 4. Evaluation of sorption behavior of iodide ions on calcium silicate hydrate and hydrotalcite; 5. Study of the release of the fission gases (Xe and Kr) and the fission products (Cs and I) under anoxic conditions in bicarbonate water; 6. Technetium getters to improve cast stone performance; 7. Selective ordering of pertechnetate at the interface between amorphous silica and water: a Poisson Boltzmann treatment; Part II. Development and Characterization of Waste Forms: 8. Pressureless sintering of sodalite waste-forms for the immobilization of pyroprocessing wastes; 9. MoO3 incorporation in alkaline earth aluminosilicate glasses; 10. Valence and local environment of molybdenum in aluminophosphate glasses for immobilization of high level waste from uranium-graphite reactor spent nuclear fuel reprocessing; 11. Copper valence and local environment in aluminophosphate glass-ceramics for immobilization of high level waste from uranium-graphite reactor spent nuclear fuel reprocessing; 12. Nepheline crystallization in high-alumina high-level waste glass; 13. Wet chemical and UV-Vis spectrometric iron speciation in quenched low and intermediate level nuclear waste glasses; 14. A sampling method for semi-quantitative and quantitative electron microprobe analysis of glass surfaces; 15. The void fraction of melter feed during nuclear waste glass vitrification; 16. Charge compensation in trivalent doped Ca3(SiO4)Cl2; 17. Effect of charge-balancing species on Sm3+ incorporation in calcium vanadinite; Part III. Corrosion Behavior of Materials: 18. Key phenomena governing HLW glass behavior in the French deep geological disposal; 19. Glass corrosion in the presence of iron-bearing materials and potential corrosion suppressors; 20. Uncertainty in the surface area of crushed glass in rate calculations; 21. About U(t) form of pH-dependence of glass corrosion rates at zero surface to volume ratio; 22. Glass degradation in performance assessment models; 23. Hierarchical modeling of HLW glass-gel-solution systems for stage 3 glass degradation; 24. Solution composition effects on the dissolution of a CeO2 analogue for UO2 and ThO2 nuclear fuels; Part IV. Storage and Disposal of Nuclear Waste: 25. Deep borehole disposal research: what have we learned from numerical modeling and what can we learn?; 26. Characteristics of cementitious paste for use in deep borehole disposal of spent fuel and high level wasteforms; 27. Physicochemical properties of vitrified forms for LILW generated from Korean nuclear power plant; 28. Release of 108Ag from irradiated PWR control rod absorbers under deep repository conditions; 29. Advancing the modelling environment for the safety assessment of the Swedish LILW repository at Forsmark; 30. Analysis of radionuclide migration with consideration of spatial and temporal change of migration parameters due to uplift and denudation; 31. Pore and mineral structure of rock using nano-tomographic imaging.

Promotional Information

Symposium EE, entitled 'Scientific Basis for Nuclear Waste Management XXXVIII', was held from 30 November to 5 December 2014, at the MRS Fall Meeting in Boston.