Chemical stability of simulated waste forms SrZrxTi1?xO3

MU Wanjun; LI Xingliang; YU Qianhong; JIAN Yuan; WEI Hongyuan; YANG Yushan

doi:10.11889/j.0253-3219.2015.hjs.38.090301

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Chemical stability of simulated waste forms SrZrxTi1?xO3

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- Chemical stability of simulated waste forms SrZrxTi1?xO3
- NUCLEAR TECHNIQUES Vol. 38, Issue 9, Article number: 090301(2015)
- 作者机构：
  
  1. 中国工程物理研究院核物理与化学研究所,绵阳,621900
  2. 西南科技大学国防学院,绵阳,621900
- 作者简介：
- 基金信息：
- DOI：10.11889/j.0253-3219.2015.hjs.38.090301
  CLC：
- Published：10 September 2015
- 稿件说明：
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MU Wanjun, LI Xingliang, YU Qianhong, et al. Chemical stability of simulated waste forms SrZrxTi1?xO3[J]. Nuclear techniques, 2015, 38(9): 090301
DOI：

MU Wanjun, LI Xingliang, YU Qianhong, et al. Chemical stability of simulated waste forms SrZrxTi1?xO3[J]. Nuclear techniques, 2015, 38(9): 090301 DOI： 10.11889/j.0253-3219.2015.hjs.38.090301.

摘要

为研究90Sr衰变子体对90SrTiO3固化体结构稳定性的影响，以C4H6O4Sr?0.5H2O、TiO2及ZrOCl2?8H2O粉体作为原料，按照化学计量比SrZrxTi1?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 5 ?g?mL?1，Zr4+的最大浸出浓度为0.01 ?g?mL?1。

Abstract

Background: 90Zr is a decay product of 90Sr

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 SrTiO3 used for immobilizing 90Zr

C4H6O4Sr?0.5H2O

TiO2 and ZrOCl2?8H2O are used as the starting materials. Methods: The Zr-doped SrTiO3 synthesized can be generally represented as SrZrxTi1?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 0.0065 ?g?mL?1 and 0.01?g?mL?1

respectively. The crystalline phase and morphology of solidified SrZrxTi1?xO3 waste form are influenced by electron beam irradiation. Conclusion: This study results may provide technical support for long-time immobilization of the 90Sr. Abstract

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