Kun Huang, Gaiyuan Chen, Xiangyang Li, Yupeng Xie, Yong Liu, Yang Yang, Yuzhen Mai, Keyou Shi
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引用次数: 0
Abstract
The safe disposal of radioactive sludge generated from the use of nuclear energy is crucial. In this study, the simulated radioactive sludge was successfully vitrified via microwave sintering with the addition of NH4H2PO4, forming Na2O-Al2O3-Fe2O3-P2O5 (SAIP) system glass, and monazite glass–ceramic was simultaneously produced. The phase evolution, microstructure, density, and chemical stability of the sintered samples were systematically researched. The results indicated that vitrification of the sintered samples can be achieved when the NH4H2PO4 content in the radioactive sludge reaches 65 wt.% at temperatures of 1200 °C and 1300 °C. The maximum solid solubility level of Nd in the glass structure was 45 wt.% at 1200 °C and 46 wt.% at 1300 °C. Moreover, the density of the sintered samples ranged from 2.62 to 3.12 g/cm3, and they exhibited excellent leaching resistance. The results of this study provide a new perspective for the safe disposal of radioactive sludge.
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.