Ran Tan, Xiaoyan Shu, Wenhong Han, Jiaqin Wei, Mingfen Wen, Zhanqiang Li, Xirui Lu
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Encapsulation of simulated nuclear waste Nd2O3 in a granite derived glass–ceramic
The experimental results showed that 9.13 wt.% of alkali metal of granite, solid solubility limit was 25 wt.%. During the transition to the glassy state and the complete vitrification period, the proportion of Q3 increased, while the proportions of Q1 decreased. When exceeding the solid solubility limit, the proportion of Q3 structure decreased, and the proportions of Q1 and Q2 structures increased. Therefore, Q3 was considered the key part of waste form. In addition, the maximum Vickers hardness was 6.06 GPa and the maximum density was 2.95 g·cm−3. After 42 d, the normalized leaching rate of Nd3+ was 4.01 × 10–8 g·m−2·d−1.
期刊介绍:
An international periodical publishing original papers, letters, review papers and short communications on nuclear chemistry. The subjects covered include: Nuclear chemistry, Radiochemistry, Radiation chemistry, Radiobiological chemistry, Environmental radiochemistry, Production and control of radioisotopes and labelled compounds, Nuclear power plant chemistry, Nuclear fuel chemistry, Radioanalytical chemistry, Radiation detection and measurement, Nuclear instrumentation and automation, etc.