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
Views 674 Downloads 49
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
Follow on us
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
To cite this article
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/
) which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.
International Atomic Energy Agency. Application of thermal technologies for processing of radioactive waste. Vienna, 2006.
Womack R. K., Shuey M. W. Development and Use of the Dualmode Plasma Torch. Tucson, Arizona, USA: Proceedings of the Waste Management Conference. 2002, pp. 200-208.
Nakashima M., Fukui T., Nakashima N., et al. Characterization of Solidified Products Yielded by Plasma Melting Treatment of Simulated Non-metallic radioactive waste. Journal of Nuclear Science and Technology. Vol. 39, No. 6, 2002, pp. 687-694.
Park J. K., Song M. J. Feasibility Study on Vitrification of Intermediate and Low Level Radioactive Waste from Pressurized Water Reactors. Waste Management. Vol. 18, No. 3, 1998, pp. 157-167.
Tzeng C. C., Kuo Y. Y., Huang T. F., et al. Treatment of Radioactive Waste by Plasma Incineration and Vitrification for Final Disposal. Journal of Hazardous Materials. Vol. 58, No. 1/3, 1998, pp. 207-220.
Xu W. B., Lv Y. H., Chen M. Z., etc.. Experimental study on simulated radioactive wastes vitrification with arc plasma. Nuclear Power Engineering. Vol. 36, No. 6, 2015, pp. 175-179.
Chen M. Z., Bai B., Liu X. J., etc.. Development of glass formulation for plasma vitrification of combustible solid wastes from nuclear power plants. Radiation Protection. Vol. 35, No. 5, 2015, pp. 262-266.
Chen M. Z., Huang W. Y., Lv Y. H., etc.. Numerical simulation and experiment of plasma torch for LILW vitrification. Nuclear Fusion and Plasma Physics. Vol. 36, No. 3, 2016, pp. 282-288.
Lin P., Lu J., Liu X. J., etc.. Investigation of thermal plasma melting of typical intermediate and low level radioactive wastes from nuclear power plant. Materials China. Vol. 35, No. 7, 2016, pp. 504-508.
Lin P., Qin Y. X., Lv Y. H., et al. Temperature Simulation of Thermal Plasma Melting Furnace for Disposal of Radioactive Waste and Preliminary Research of Vitrification Formula. Radiation Protection. Vol. 33, No. 4, 2013, pp. 206-211.
Commission on Science, Technology and Industry for National Defense. EJ 1186-2005, Characterization of Radioactive Waste Forms and Packages. Beijing: China Environmental Science Press, 2005-04-11.
Ministry of Environment Protection, General Administration of Quality Supervision, Inspection and Quarantine of the People’s Republic of China. GB 14569.1-2011, Performance Requirements for Intermediate and Low Level Radioactive Waste Form – Cemented Waste Form. Beijing: China Environmental Science Press, 2011-09-01.
Standardization Administration of the People’s Republic of China. GB/T 475-2008, Method for Manual Sampling of Commercial Coal. Beijing: Standards Press of China, 2009-05-01.
Standardization Administration of the People’s Republic of China. GB/T 5432-2008, Test Method for Density of Glass by Buoyancy. Beijing: Standards Press of China, 2009-04-01.
ASTM International. ASTM C1220-17, Standard Test Method for Static Leaching of Monolithic Waste Forms for Disposal of Radioactive Waste. West Conshohocken, PA, 2017, www.astm.org.
Standardization Administration of the People’s Republic of China. Test Method for Compressive Strength of Fine Ceramics (Advanced Ceramics, Advanced technical ceramics), GB/T 8489-2006. Beijing: Standards Press of China, 2006-09-01.