Researchers from fifteen countries come together in this volume to focus on materials-related issues associated with nuclear waste management. Invited and contributed papers cover a wide range of topics including: national research programs; advanced fuel cycles; behavior of spent nuclear fuel; nuclear waste glasses and vitrification; ceramic waste forms; engineered barrier systems and the near field; cementitious waste forms; geological disposal; container corrosion; waste-form performance and natural analogues; and migration and colloids. Long-term performance and corrosion issues at the Yucca Mountain Repository are also featured, as are presentations from a joint session with Symposium O, Structure/Property Relationships in Fluorite-Derivative Compounds, on actinide fuels and waste forms.
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