Journal of the Korean Ceramic Society (한국세라믹학회지)

The Korean Ceramic Society (한국세라믹학회)
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Evaluation of Characteristics of Simulated Radioactive Vitrified Form Using Cooling Methods

냉각 방법에 따른 모의 방사성폐기물 유리고화체의 특성평가

  • Lee, Kang-Taek (School of Materials Science and Engineering, Pusan National University) ;
  • Lee, Kyu-Ho (School of Materials Science and Engineering, Pusan National University) ;
  • Yoon, Duk-Ki (School of Materials Science and Engineering, Pusan National University) ;
  • Ryu, Bong-Ki (School of Materials Science and Engineering, Pusan National University) ;
  • Kim, Cheon-Woo (Nuclear Engineering and Technology Institute, Korea Hydro and Nuclear Power Co., Ltd.) ;
  • Park, Jong-Kil (Nuclear Engineering and Technology Institute, Korea Hydro and Nuclear Power Co., Ltd.) ;
  • Hwang, Tae-Won (Nuclear Engineering and Technology Institute, Korea Hydro and Nuclear Power Co., Ltd.)
  • 이강택 (부산대학교 재료공학과) ;
  • 이규호 (부산대학교 재료공학과) ;
  • 윤덕기 (부산대학교 재료공학과) ;
  • 류봉기 (부산대학교 재료공학과) ;
  • 김천우 (한국수력원자력(주) 원자력발전기술원) ;
  • 박종길 (한국수력원자력(주) 원자력발전기술원) ;
  • 황태원 (한국수력원자력(주) 원자력발전기술원)
  • Published : 2006.12.31
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Abstract

In order to examine and compare the characteristics of two vitrified forms (AG8W1 and DG2) simulated for the operation of a commercial vitrification facility being constructed in Ulchin nuclear power plant, the vitrified forms were cooled by the natural cooling and annealing methods respectively. And the Product Consistency Test (PCT), compressive strength, thermal conductivity, specific heat, phase stability, softening point and Coefficient of Thermal Expansion (CTE) of the vitrified farms were experimented. Consequently, it was shown that there were no significant differences on the physiochemical properties of the vitrified forms performed the natural cooling and annealing.

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References

  1. W. Vogel, Glass Chemistry, 2nd Ed., pp. 22-33, Springer Verlag, New York, 1992
  2. H. Scholze, Glass Science, pp. 237-61, Translated by Lee Joung Heon, Chong Moon Gak, 1995
  3. R. H. Doremus, Glass Science, 2nd Ed., pp. 13-22, John Wiley & Sons Inc., New York, 1994
  4. M. B. Volf, Chemical Approach to Glass, pp. 35-61, Elsevier, New York, 1984
  5. L. D. Pye, H. J. Stevens, et al., Introduction to Glass Science, pp. 29-41, Plenum Press, 1972
  6. A. Paul, Chemistry of Glasses, pp. 137-71, Chapman and Hall, 1990
  7. W. Lutze, R. C. Ewing, Eds., Radioactive Waste Forms for the Future, pp. 131-44, North Holland, Amsterdam, 1988
  8. C. N. Wilson, Ed., Evaluation of Melter Technologies for Vitrification of Hanford Site Low Level Tank Waste Phase I Testing Summary Report, WHC SD WMER 498, Revision 0, 1996
  9. IAEA, Regulations for the Safe Transport of Radioactive Material, Safety Standards Series No. ST 1, Vienna (1996)
  10. IAEA Technical Reports Series No. 176, Techniques for the Solidification of High Level Wastes, International Atomic Energy Agency, Vienna, 1977
  11. IAEA Technical Reports Series No. 187, Characteristics of Solidified High Level Waste Products, International Atomic Energy Agency, Vienna, 1979
  12. IAEA Technical Reports Series No. 339, Design and Operation of High Level Waste Vitrification and Storage Facilities, pp. 10-81, International Atomic Energy Agency, Vienna, 1992
  13. US EPA, Vitrification Technologies for Treatment of Hazardous and Radioactive Waste, April, 1992
  14. C.-W. Kim, J.-Y. Kim, S.-J. Maeng, J.-K. Park, and T.-W. Hwang, 'Evaluation of Chemical Durability of Vitrified Forms for Simulated Radioactive Waste Using Product Consistency Test(PCT) and Vapor Hydration Test(VHT)(in Korean),' J. Kor. Rad. Waste Soc., 4 [3] 227-34 (2006)
  15. C. M. Jantzen and N. E. Bibler, Product Consitency Tests (PCT) Method Version 3.0, WSRC TR 90 539, Westinghouse Savannah River Laboratory, Aiken, SC, 1989