Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT) (방사성폐기물학회지)

Korean Radioactive Waste Society (한국방사성폐기물학회)
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Physicochemical Property of Borosilicate Glass for Rare Earth Waste From the PyroGreen Process

  • Young Hwan Hwang (Central Research Institute, Korea Hydro & Nuclear Power) ;
  • Mi-Hyun Lee (Central Research Institute, Korea Hydro & Nuclear Power) ;
  • Cheon-Woo Kim (Central Research Institute, Korea Hydro & Nuclear Power)
  • Received : 2023.01.23
  • Accepted : 2023.03.06
  • Published : 2023.06.30
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Abstract

A study was conducted on the vitrification of the rare earth oxide waste generated from the PyroGreen process. The target rare earth waste consisted of eight elements: Nd, Ce, La, Pr, Sm, Y, Gd, and Eu. The waste loading of the rare earth waste in the developed borosilicate glass system was 20wt%. The fabricated glass, processed at 1,200℃, exhibited uniform and homogeneous surface without any crystallization and precipitation. The viscosity and electrical conductivity of the melted glass at 1,200℃ were 7.2 poise and 1.1 S·cm-1, respectively, that were suitable for the operation of the vitrification facility. The calculated leaching index of Cs, Co, and Sr were 10.4, 10.6, and 9.8, respectively. The evaluated Product Consistency Test (PCT) normalized release of the glass indicated that the glass satisfied the requirements for the disposal acceptance criteria. Furthermore, the pristine, 90 days water immersed, 30 thermal cycled, and 10 MGy gamma ray irradiated glasses exhibited good compressive strength. The results indicated that the fabricated glass containing rare earth waste from the PyroGreen process was acceptable for the disposal in the repository, in terms of chemical durability and mechanical strength.

Keywords

Acknowledgement

This work was supported by the National Research Foundation of Korea (NRF) grant funded by the Ministry of Science, ICT and Future Planning, Republic of Korea (MSIP) (NRF-2011-0031839, NRF-2011-0031890).

References

  1. H. Jung, S. Choi, and I.S. Hwang, "Safe, Secure, and Clean Disposal of Final Nuclear Wastes Using 'PyroGree' Strategies", Proc. of the 10th International Conference, GLOBAL 2011, Atomic Energy Society of Japan, Tokyo (2011). 
  2. T.G. Lee, Y.J. Jo, H.C. Yang, H.S. Lee, and I.T. Kim, "Recycling Technology of Eutectic Salt Waste Generated in Oxide Spent Fuel Pyroprocessing", Proc. of the 2009 Autumn Conference, vol. 7(2), 169-170, The Korean Radioactive Waste Society, Jeju (2009). 
  3. R. Noyes, Nuclear Waste Cleanup Technologies and Opportunities, Noyes Publications, New Jersey (1995). 
  4. D.K. Morrell and D.K. Fischer. Department of Energy Treatment Capabilities for Greater-Than-Class C Low-Level Radioactive Waste, U.S. Department of Energy Report, DOE/LLW-203 (1995). 
  5. C. Lopez, X. Deschanels, J.M. Bart, J.M. Boubals, C. Den Auwer, and E. Simoni, "Solubility of Actinide Surrogates in Nuclear Glasses", J. Nucl. Mater., 312(1), 76- 80 (2003).  https://doi.org/10.1016/S0022-3115(02)01549-0
  6. M.I. Ojovan and W.E. Lee, An Introduction to Nuclear Waste Immobilization, Elsevier, Amsterdam (2005). 
  7. H. Zhang, C.L. Corkhill, P.G. Heath, R.J. Hand, M.C. Stennett, and N.C. Hyatt, "Effect of Zn- and Ca-oxides on the Structure and Chemical Durability of Simulant Alkali Borosilicate Glasses for Immobilisation of UK High Level Waste", J. Nucl. Mater., 462, 321-328 (2015).  https://doi.org/10.1016/j.jnucmat.2015.04.016
  8. S.V. Mattigod, J.H. Westsik Jr., C.W. Chung, M.J. Lindberg, and K.E. Parker. Waste Acceptance Testing of Secondary Waste Forms: Cast Stone, Ceramicrete and DuraLith, Pacific Northwest National Laboratory Technical Report, PNNL-20632 (2011). 
  9. R.L. Russell, M.J. Schweiger, J.H. Westsik, Jr., P.R. Hrma, D.E. Smith, A.B. Gallegos, M.R. Telander, and S.G. Pitman. Low Temperature Waste Immobilization Testing, Pacific Northwest National Laboratory Technical Report, PNNL-16052 Rev. 1 (2006). 
  10. American Nuclear Society, Measurement of the Leachability of Solidified Low-Level Radioactive Wastes by a Short-Term Test Procedure, ANSI/ANS-16.1-2003 (2003). 
  11. American Society for Testing and Materials, Standard Test Methods for Determining Chemical Durability of Nuclear, Hazardous, and Mixed Waste Glasses: The Product Consistency Test (PCT), ASTM C1298-97, West Conshohoken, Pennsylvania (1997). 
  12. K. Vinjamuri, S.T. Wood, and L. O. Nelson, GlassForm-Version 1.1: An Algorithm for Generating Preliminary Glass Formulations for Waste Streams, INEEL/EXT-98-00269 (2000). 
  13. C.W. Kim, K.O. Cho, Y.P. Moon, S.C. Park, S.J. Maeng, J.K. Park, T.W. Hwang, S.W. Shin, K.H. Lee, and B.K. Ryu, "Studies on the Physicochemical Properties of Borosilicate Glass Developed for Radioactive Waste", J. Ceram. Soc. Japan, 116(1351), 497-499 (2008).  https://doi.org/10.2109/jcersj2.116.497
  14. H.S Jung, K.D. Kim, S.H. Lee, S.K. Kwon, C.W. Kim, J.K. Park, T.W. Hwang, and Z.S. Ahn, "Characterization of Glass Melts Containing Simulated Low and Intermediate Level Radioactive Waste", J. Korean Ceram. Soc., 43(3), 148-151 (2006).  https://doi.org/10.4191/KCERS.2006.43.3.148
  15. J.E. Shelby, Introduction to Glass Science and Technology, 2nd ed., The Royal Society of Chemistry, Cambridge (2005). 
  16. J. Stanek, Electric Melting of Glass, Elsevier Scientific Publishing, Amsterdam (1977).