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Uptake of radionuclides on microporous and layered ion exchange materials

机译:在微孔和层状离子交换材料上吸收放射性核素

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摘要

Titanosilicatesm,layered manganese oxides and an antimonysilicate were tested for their ability to take up the reprocessing spent fuel transuranium isotopes americium-241 and plutonium-236.This was performed in different concentrations of acid and sodium and calcium nitrate solutions to represent the conditions of nuclear waste treatment.The purpose was to assess the waste types (acidic or low-medium-high-salt) most suited to treatment by these materials.The experiments were carried oiut by the batch method and the results obtained expressed as distribution coefficients.Variation in the magnitude and mechanism of actinide sorption by the materials was attributed to the differences in the frameworks,physical properties (porosity,crystal size and chemical composition) and surface charges of the ion exchanges.In nitric acid solutions,the H-antimonysilicate proved to b a better sorbent than H-birnessite for both actinide elements.The void space of AM-4 layered titanosilicate material made it appropriate for actinide removal in sodium salt solutions.The differences in selectivity of Ca-antimonysilicate and Ca-birnessite for americium-241 and plutonium-236 in 0.01 M calcium nitrate solution reflected the preference of each material for actinides over calcium ions.
机译:测试了钛硅酸盐,层状锰氧化物和锑硅酸盐吸收乏燃料超铀同位素a 241和p 236的能力,该过程在不同浓度的酸,钠和硝酸钙溶液中进行,以代表核条件目的是评估最适合用这些材料处理的废物类型(酸性或低中高盐分)。分批方法进行了实验,所得结果用分布系数表示。材料对of系元素的吸附程度和机理归因于离子交换的构架,物理性质(孔隙度,晶体大小和化学组成)和表面电荷的差异。在硝酸溶液中,H-锑硅酸盐证明可以两种act系元素都比H-水钠锰石更好的吸附剂.AM-4层状钛硅酸盐材料的空隙空间在0.01 M的硝酸钙溶液中,钙锑硅酸盐和钙水钠锰矿对ite 241和236 236的选择性差异反映了每种材料对act系元素的偏好高于钙离子。

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