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Basic Research Needs for Geosciences - Energetics Meetings and ...

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APPENDIX 1: TECHNICAL PERSPECTIVES RESOURCE DOCUMENTfocused on spent nuclear fuel; other waste <strong>for</strong>ms (e.g., glasses, ceramics, metals) would havesimilar needs but some specifics would change (e.g., no role of cladding <strong>for</strong> other waste <strong>for</strong>ms).A closed fuel cycle requires a geologic repository <strong>for</strong> disposal of long-lived fission products <strong>and</strong>potentially very small amounts of actinides, the latter being from minor separations processlosses. Potential waste <strong>for</strong>m materials—oxides, glasses, <strong>and</strong>/or metals—containing radionuclidesare key components of the repository system. The potentially significant doses from the encasedradionuclides require long-term isolation in durable waste <strong>for</strong>ms. As part of ef<strong>for</strong>ts in the U.S.<strong>and</strong> worldwide to develop advanced nuclear fuel cycles, additional research is required toidentify potential advanced waste <strong>for</strong>m materials (see Lutze <strong>and</strong> Ewing 1988 <strong>and</strong> referencestherein; Ewing et al. 2004). If c<strong>and</strong>idate advanced waste <strong>for</strong>m materials are further developed,focused work to increase underst<strong>and</strong>ing of waste <strong>for</strong>m per<strong>for</strong>mance in complex geologic settingsis needed. Prediction of geologic repository per<strong>for</strong>mance to 10 4 years (<strong>and</strong> even 10 6 years), <strong>and</strong>the role of the source term in long-term safety, represent unprecedented scientific challenges.To provide durable waste <strong>for</strong>ms <strong>and</strong> demonstrate their long-term per<strong>for</strong>mance, the behavior ofmaterials must be understood at a level of fundamental knowledge <strong>and</strong> predictability that couldallow <strong>for</strong> reduction in the conservatism of engineered system designs, while still achieving therequired safety margins, <strong>and</strong> perhaps lowering repository costs. The waste <strong>for</strong>m materials <strong>for</strong>mcomplex multi-component dynamic systems that evolve in time over a wide range of conditionsincluding high radiation fields, high temperatures, <strong>and</strong> potentially corrosive chemicalenvironments (see Lutze <strong>and</strong> Ewing 1988 <strong>and</strong> references therein; Smith et al. 1992).Fundamental underst<strong>and</strong>ing of the properties of waste <strong>for</strong>ms is essential to predicting their longtermbehavior <strong>and</strong> can only result from closely coupled theory, modeling, <strong>and</strong> experimentation.A fundamental <strong>and</strong> integrated experimental <strong>and</strong> modeling approach to source term processes, asdescribed above <strong>for</strong> spent nuclear fuel, can also be readily applied to development of advancedwaste <strong>for</strong>ms as part of a closed nuclear fuel cycle. Specifically, a fundamental underst<strong>and</strong>ing ofthe stability of c<strong>and</strong>idate advanced waste <strong>for</strong>m materials in high temperature/high radiationenvironments <strong>and</strong> near-field geochemical/hydrologic processes could enable development ofwaste <strong>for</strong>ms “tailored” to specific geologic settings (Lutze <strong>and</strong> Ewing 1988). Closing the fuelcycle will generate a new class of waste <strong>for</strong>ms with a different chemical composition, differentthermal <strong>and</strong> radiation profiles <strong>and</strong> time evolutions, <strong>and</strong> different requirements <strong>for</strong> wastepackaging, interim storage, <strong>and</strong> long-term disposition. Technical challenges include:1. Immobilization of high-heat fission products (cesium, strontium) <strong>and</strong> long-lived fissionproducts (iodine, technetium) in tailored storage/waste <strong>for</strong>ms2. Higher fission-product loadings <strong>for</strong> ceramic waste-<strong>for</strong>m technologies3. Determination of thermodynamic <strong>and</strong> thermophysical properties of actinide-containing waste<strong>for</strong>ms, including radiation effects, transport, <strong>and</strong> interfacial interactions4. New geologic waste-<strong>for</strong>m materials tailored <strong>for</strong> reduced actinides <strong>and</strong> increased fissionproductsSee DOE 2006a <strong>for</strong> detailed discussions.<strong>Basic</strong> <strong>Research</strong> <strong>Needs</strong> <strong>for</strong> <strong>Geosciences</strong>: Facilitating 21 st Century Energy Systems Appendix 1 • 37

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