An Experimental Study on Treatment of Typical Low and Intermediate Level Radioactive Wastes with Thermal Plasma Melting Technology
International Journal of Materials Science and Applications
Volume 7, Issue 4, July 2018, Pages: 147-152
Received: Jun. 3, 2018;
Accepted: Jul. 19, 2018;
Published: Aug. 21, 2018
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Wenzhang Xie, Environment Engineering Center, China Nuclear Power Technology Research Institute, Shenzhen, China
Peng Lin, Environment Engineering Center, China Nuclear Power Technology Research Institute, Shenzhen, China
Jie Lu, Environment Engineering Center, China Nuclear Power Technology Research Institute, Shenzhen, China
Xiajie Liu, Environment Engineering Center, China Nuclear Power Technology Research Institute, Shenzhen, China
Mingzhou Chen, Environment Engineering Center, China Nuclear Power Technology Research Institute, Shenzhen, China
Yonghong Lv, Environment Engineering Center, China Nuclear Power Technology Research Institute, Shenzhen, China
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With the active development of the nuclear industry in China, it is extremely urgent to study and develop advanced technologies for the radioactive waste treatment and disposal. With features of high temperature, high energy density and broad applicability, the thermal plasma melting technology has been considered as one of the key subjects in the radioactive waste treatment research field. A pilot scale experimental study was carried out on the treatment of typical low and intermediate level radioactive wastes (LILWs) from the nuclear power plant in China with thermal plasma melting technology. Two representative wastes, thermal insulation waste and cotton, were selected and melted in the plasma melting furnance at 1250°C for ~ 100 minutes until they were completely vitrified. Meanwhile, tracers of Co2O3, CsCl and SrCO3 were added to the original wastes to simulate the containment effect of 58Co and 60Co, 134Cs and 137Cs as well as 90Sr in the vitrification during the treatment process. The XRD patterns of both vitrification samples displayed as the typical amorphous state. Performances of resultant glass waste-forms, including the physical property, the leachability and the mechanical capacity, were in accordance with the standard requirements of the hign level radioactive waste glass vitrificaton, and were better than those of the cement solidified waste. Further experimental work is in need to better understand the radioactive nuclide migration regularity and to improve the performance of the plasma melting system.
LILW, Thermal Plasma, Glass Vitrification
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An Experimental Study on Treatment of Typical Low and Intermediate Level Radioactive Wastes with Thermal Plasma Melting Technology, International Journal of Materials Science and Applications.
Vol. 7, No. 4,
2018, pp. 147-152.
Copyright © 2018 Authors retain the copyright of this article.
This article is an open access article distributed under the Creative Commons Attribution License (http://creativecommons.org/licenses/by/4.0/
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