Chemical Durability of Simulated Waste Glasses

모의 폐기물유리의 화학적 내구성

  • 현상훈 (연세대학교 요업공학과) ;
  • 송원선 (연세대학교 요업공학과)
  • Published : 1989.04.01

Abstract

The dependence of the chemical durability of simulated waste glasses containing the simplified waste similar to the SRP waste on compositions of host glasses, amounts of waste loading, and kinds of leachants has been investigated as a basic study on the waste immobilization through vitrification. The maximum limit of the amount of waste loading for glassforming with the host sodium borosilicate glasses selected in this study was 50wt%. The chemical durability of waste glasses whose host glass belonged to the immiscible composition region was much higher than that of waste glasses whose host glass belonged to the miscible composition region. The former waste glass showed lower chemical durability in deionized and silicate waters than in brine, while the latter glass showed the lowest chemical durability in deionized and silicate waters than in brine, while the latter glass showed the lowest chemical durability in silicate water. It was also observed that the total leaching rates in brine were noticeably small in comparison with those in other solutions. The composition of the host borosilicate glass which was suitable for the treatment of the waste through vitrification was found to be 25 Na2O-5B2O3-70SiO2(wt.%).

Keywords

References

  1. J. Am. Ceram. Soc. v.67 Sodium Diffusion and Leaching of Simulated Nuclear Waste Glass B.P. Mcgrail;A. Kumar;D.E. Day
  2. J. Am. Ceram. Soc. v.66 Chemical Durability of Savannah River Plant Waste Glass as a Function of Waste Loading W.D. Rankin;G.G. Wicks
  3. J. Non-Cryst. Solids v.84 Vitrification Chemistry and Nuclear Waste M.J. Plodinec
  4. J. Non-Cryst. Solids v.67 Thermodynamic Model of Natural, Medieval and Nuclear Waste Glass Durability C.M. Jantzen;M.J. Plodinec
  5. J. Non-Cryst. Solids v.67 Surface Layer Formation on Corroded Nuclear Waste Glasses B.C. Sales;C.W. White;G.M. Begun;L.A. Boatner
  6. J. Non-Cryst. Solids v.49 Effects of Surfaces on Glass Waste Form Leaching C. Pescatore;A.J. Machiels
  7. J. Am. Ceram. Soc. v.64 The High-Silica Liquidus surface of the System Na₂O-B₂O₃-SiO₂ T.J. Rockett;W.R. Foster
  8. Nucl. Technol. v.56 MCC-1 : Standard Leach Test for Nuclear Waste Forms D.M. Strachan;R.P. Turcotte;P.O. Barmes
  9. J. Am. Ceram. Soc. v.69 Investigation of Foaming in Liquid-Fed Melting of Simulated Nuclear Waste Glass D.S. Goldman;D.W. Brite;W.C. Richey
  10. 연세대학교 대학원 석사 학위논문 붕규산 소다 유리의 상분리 및 화학적 내구성에 대한 첨가제의 영향 천광수
  11. J Kor. Ceram. Soc. v.25 Effects of Additives on the Phase Separation and the Chemical Durability of Sodium Borosilicate Glasses S.H. Hyun;K.S. Cheon;W.S. Song
  12. Am. Ceram. Soc. Bull. v.62 Optimization of Glass Composition for the Vitrification of Nuclear Waste at the Savannah River Plant D.D. Soper;D.D. Walker;M.J. Plodinec