【摘要】 为研究90Sr衰变子体对90Sr Ti O3固化体结构稳定性的影响,以C4H6O4Sr·0.5H2O、Ti O2及Zr OCl2·8H2O粉体作为原料,按照化学计量比Sr ZrxTi1-xO3(0≤x<1)设计配方,采用高温固相法制备一系列固化体。利用X射线衍射光谱(X-ray Diffraction,XRD)、扫描电镜(Scanning Electron Microscope,SEM)及红外(Fourier Transform Infrared,FT-IR)谱仪对制备固化体的物相、结构和微观形貌进行分析表征,并对其抗浸出性能和辐照性能进行了研究。结果表明,当x<0.5时,固化体为单一物相;当x≥0.5时,固化体中出现第二相。固化体中的Sr2+、Zr4+的浸出浓度随浸泡时间而增大,在浸泡42 d时,Sr2+的最大浸出浓度为0.006 5μg?m L-1,Zr4+的最大浸出浓度为0.01μg?m L-1。更多还原

【Abstract】 Background: 90 Zr is a decay product of 90 Sr, which may induce structural changes of radioactive waster forms. Purpose: In order to study the influence of decay product on the stability of perovskite-type Sr Ti O3 used for immobilizing 90 Zr, C4H6O4Sr?0.5H2 O, Ti O2 and Zr OCl2?8H2O are used as the starting materials. Methods: The Zr-doped Sr Ti O3 synthesized can be generally represented as Sr ZrxTi1-xO3(0≤x<1) with the high temperature solid reaction. The phases, structure and microcosmic shape of synthetic condensates were characterized by the X-ray Diffraction(XRD), Scanning Electron Microscope(SEM) and Fourier Transform Infrared(FT-IR), and long-term chemical stability was studied at constant temperature of 90 oC. Results: The results indicate that the second phase of compounds is observed when the value of x is more than 0.5. The leaching rate of Sr2+ and Zr4+ in waste forms increase with the immersion time, while the highest leaching ratios for 42 d are no more than 0.006 5 μg?m L-1 and 0.01 μg?m L-1, respectively. The crystalline phase and morphology of solidified Sr ZrxTi1-xO3 waste form are influenced by electron beam irradiation. Conclusion: This study results may provide technical support for long-time immobilization of the 90 Sr.更多还原