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Technetium and Molybdenum in Oxide Spent Nuclear Fuel: Impact on Release Estimates

机译:氧化物废核燃料中的and和钼:对释放量估计值的影响

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Technetium-99 (~(99)Tc) is an important radionuclide in repository models owing to its relatively long half-life and the high aqueous solubility of compounds where it is in the heptavalent state. The vast majority of the ~(99)Tc inventory presently slated for disposal is contained in oxide commercial spent nuclear fuel (CSNF), where it is divided (along with its cohort, molybdenum) between exsolved, intermetallic "epsilon" particles and isolated, likely oxidized, atoms distributed in the uranium dioxide matrix. We present recent evidence from synchrotron x-ray fluorescence spectroscopy, electron microscopy, and fuel dissolution testing on the likely oxidation state, coordination environment, and physical disposition of technetium and molybdenum in CSNF. Effects of the relative proportioning of technetium and molybdenum among the metallic and oxidized states in CSNF, and their distribution in or near grain boundaries and gaps on release during CSNF corrosion testing are discussed.
机译:net-99(〜(99)Tc)由于其相对较长的半衰期和处于七价状态的化合物的高水溶性而在存储库模型中是重要的放射性核素。目前预定处置的〜(99)Tc绝大部分库存都包含在氧化物商业乏核燃料(CSNF)中,在那里将其分解(连同其同族,钼)在已溶解的金属间“ε”颗粒之间进行分离,可能被氧化的原子分布在二氧化铀基质中。我们提供了来自同步加速器X射线荧光光谱法,电子显微镜和燃料溶解测试的最新证据,这些燃料对CSNF中可能存在的氧化态,配位环境以及of和钼的物理处置进行了测试。讨论了CSNF中金属态和氧化态中of和钼的相对比例及其在晶界和间隙中或附近的分布对CSNF腐蚀测试中释放的影响。

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