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A comparison of radiation effects in crystalline ABO_4-type phosphates and silicates

机译:晶体ABO_4型磷酸盐和硅酸盐中辐射效应的比较

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The effects of ion irradiation in the ADO_4-typC compounds were compared by performing experiments on four materials that include the most common crystal structures (monazite vs. zircon) and chemical compositions (phosphates vs. silicates) for these phases. Pure synthetic single crystals of ZrSiO_4, monoclinic ThSiO_4, LaPO_4 and ScPO_4 were irradiated using 800 keV Kr ions. Radiation damage accumulation was monitored as a function of temperature in situ in a transmission electron microscope. The activation energies for recrystallization during irradiation were calculated to be 3.1-3.3 eV for the orthosilicates but only 1.0- t .5 eV for the isostructural orthophosphates. For the ion-beam-irradiated samples, the critical temperature, above which the recrystallization processes are faster than damage accumulation and amorphization cannot be induced, is >700 deg C for ZrSiO_4 but it is only 35 deg C for LaPO_4. At temperatures above 600 deg C, zircon decomposed during irradiation into its component oxides (i.e. crystalline ZrO_2 plus amorphous SiO_2). The data are evaluated with respect to the proposed use of the orthophosphates and orthosilicates as host materials for the stabilization and disposal of high-level nuclear waste. The results show that zircon with 10 wt. percent Pu would have to be maintained at temperatures in excess of 300 deg C in order to prevent it from becoming completely amorphous. In contrast, a similar analysis for the orthophosphates implies that monazite-based waste forms would not become amorphous or undergo a phase decomposition.
机译:通过对四种材料进行实验比较了离子对ADO_4-typC化合物的影响,这些材料包括这些相中最常见的晶体结构(独居石与锆石)和化学成分(磷酸盐与硅酸盐)。使用800 keV Kr离子辐照ZrSiO_4,单斜晶ThSiO_4,LaPO_4和ScPO_4的纯合成单晶。在透射电子显微镜中监测辐射损伤积累与温度的关系。对于正硅酸盐,在辐射过程中用于重结晶的活化能经计算为3.1-3.3 eV,而对于同结构正磷酸盐,其活化能仅为1.0-t 0.5 eV。对于离子束辐照的样品,ZrSiO_4的临界温度高于700摄氏度,而LaPO_4仅为35摄氏度,高于该临界温度再结晶过程比损伤积累和非晶化快。在高于600摄氏度的温度下,锆石在辐照过程中分解成其成分氧化物(即晶体ZrO_2加无定形SiO_2)。就建议使用正磷酸盐和正硅酸盐作为稳定和处置高含量核废料的主体材料评估了数据。结果表明,锆石含10wt。%的锆石。为了防止其完全变成非晶态,必须将100%的Pu保持在超过300℃的温度下。相反,对正磷酸盐的类似分析表明,独居石基废物形式不会变成非晶态或发生相分解。

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