Korean Chemical Engineering Research

The Korean Institute of Chemical Engineers (한국화학공학회)
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Distribution Characteristics of Radionuclies (60Co, 137Cs) During the Melting of Radioactive Metal Waste

방사성 금속폐기물의 용융시 방사성 핵종(60Co, 137Cs)의 분배특성

  • Received : 2007.05.15
  • Accepted : 2007.07.03
  • Published : 2007.12.31
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Abstract

A fundamental study on the melt decontamination of metal wastes generated by dismantling the nuclear facility, the melting of metal wastes such as stainless steel and carbon steel have been carried out to investigate the distribution phenomena of the radioisotopes such as $^{60}Co$ and $^{137}Cs$ into the ingot, slag and dust phases by using the various slag types, slag concentration and basicity in an arc furnace. The $^{60}Co$ remained homogeneously in the ingot phase above 90 % and it was barely present in the slag below 10 %. The effect of the slag composition on the distribution for Co-60 was not considerable, but a basic slag former with high fluidity showed effective. $^{137}Cs$ was completely eliminated from the melt of the stainless steel as well as the carbon steel and distributed to the slag and the dust phase.

원자력 시설 해체시 발생되는 금속성 폐기물의 용융 제염을 위한 기초 연구를 위해 아크 용융로를 사용하여 스테인레스강과 탄소강의 금속 폐기물 용융시 슬래그 종류, 농도, 염기도에 따라 $^{60}Co$, $^{137}Cs$ 핵종의 주괴, 슬래그, 분진 상으로 분배 특성을 살펴보았다. $^{60}Co$은 90% 이상 주괴상에 균질하게 분포되었으며, 슬래그 상에는 약 10% 미만으로 잔존하며 슬래그 조성에 따라 분배특성이 크게 영향을 받지 않았으나, 유동성이 좋은 염기성 슬래그 형성제가 포함된 슬래그에서는 영향을 받음을 알 수 있었다. $^{137}Cs$는 스테인레스강과 탄소강의 용융체로부터 완전히 제거되어 슬래그상과 분진상 상으로 분배됨을 알 수 있었다.

Keywords

References

  1. Grbener, K. H., Beyer, H. and Westermann, H., 'Melting Aluminium and Copper on Laboratory and Industrial Scale,' Proceeding of Technical Seminar on Melting and Recycling of Metallic Waste Materials from Decommissioning of Nuclear Installations, European Commission, Germany, 209-224(1993)
  2. Bosse, H., Sappok, M., Westermann, H., Dmpelmann, W. and Steiner, H., 'Separation of Metals by Melting,' Proceeding of Technical Seminar on Melting and Recycling of Metallic Waste Materials from Decommissioning of Nuclear Installations, European Commission, Germany, 225-236(1993)
  3. Eddy, T. L., Ravio, B. B., Solelberg, N. R. and Wiersholm, O., 'Advanced Mixed Waste Treatment Project Melter System Preliminary Design Technical Review Meeting,' Idaho National Engineering Laboratory, INEL-95/0054(1995)
  4. Min, B. Y., 'Low & Intermediate Level Radioactive Waste Vitrification Using Plasma Arc Melting Technology,' J. Korean Nuclear Soc., 35(5), 482-496(2003)
  5. Garcia, R. S., 'Commercially Available Low-Level Radioactive and Mixed Waste Treatment Technologies,' INEL & Locked-Martin Technologies Company(1996)
  6. Min, B. Y., Song, P. S., Ahn, J. H., Choi, W. K., Chong, C. H. and Oh, W. Z., 'Melting Characteristic for Radioactive Aluminum Waste in Electric Arc Furnace,' J. Korean Radioactive Waste Soc., 4(1), 33-40(2006)
  7. Sappok, M. and Graebener, K. H., 'Results of Melting Large Quantities of Radioactive Metallic Scrap,' Proceedings of the International Topical Meeting on Nuclear and Hazardous Waste Management, Spectrum 92, American Nuclear Society, Illinois, 120(1992)
  8. Peuive, J., 'Dismantling of Nuclear Facilities Scrap Steel Management of Scrap Metal steel Management of G2 and G3 Reactors at Marcoule,' UDIN, Commissariat AL'Energie Atomique, Marcoule, 16(1993)
  9. Jantzen, C. M., Bickford, D. F., Brown, K. G., Cozzi, A. D. and Herman, C. C., 'Savannah River Site Waste Vitrification Projects Initiated Throughout the United States,' Westinghouse Savannah River Co., Aiken, SC. Department of Energy, Washington, DC(2004)
  10. Barnes, C. M. and Taylor, D. D., 'Review of FY 2001 Development Work for Vitrification of Sodium Bearing Waste,' Idaho National Engineering and Environmental Laboratory, Idaho Falls, INEEL/EXT-02-00194(2002)
  11. Menon, S., Hernborg, G. and Anderddon, L., 'Melting of Low-Level Contaminated Steels,' Decommissioning Nuclear Installations-1990, Studsvik AB, Sweden, 497(1990)
  12. Gomer, C. R. and Lambley, J. T., 'Melting of Contaminated Steel Scrap Arising in the Dismantling of Nuclear Power Plants,' CONF-840524, United Kingdom(1984)
  13. Nakamura, H. and Fujiki, K., 'Radioactive Metal Melting Test at Japan Atomic Energy Research Institute,' Proceedings Waste Management, 1993, 2, 1688(1993)
  14. Schuster, E. and Haas, W., 'Behavior of Difficult to Measure Radionuclides in the Melting of Steel,' EUR-12690, Belgium, Elsvier applied Science, 20(1990)
  15. Kellogg, H. H. and Basu, H. K., 'The Roasting of Sulfide Ores,' Transactions, AIME, 218, 70-80(1960)
  16. Pehlke, R. D. Unit Processes of Extractive Metallurgy, Elsevier, New York(1973)
  17. Roine, A., 'SC Chemistry for Windows-Chemical Reaction and Equili brium Software with Extensive Thermochemical Database, Version 1.10,' Outokumpu Research Oy, Pori, Finland(1993)
  18. Larsen, M. M., Davis, J. N. and Logan, J. A., 'Sizing and Melting Development Activities Using Contaminated Metal at the Waste Experimental Reduction Facility,' EGG-2411 EG&G Idaho, Inc., (1985)
  19. Harvey, D. S., 'Research into the Melting/refining of Contaminated Steel Scrap Arising in the Dismantling of Nuclear Installations,' EUR-12605, commission of the european communities(1990)