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Simulation of the Waste Glass Behavior in a Loamy Soil of the Wet Repository Site

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Abstract

A model developed for description of waste glass corrosion has been applied to assess the radionuclide release from real radioactive (intermediate level) vitrified material over extended storage periods. Field data generated during the long-term testing of the prototype waste glass packages were mathematically processed and the derived parameters used in model calculations. Regardless of the corrosive saturated conditions of the wet near-surface repository, the fairly high safety of trench disposal has been demonstrated for borosilicate glass containing real NPP- operational waste.

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References

  1. Long term tests of low and intermediate level waste packages under field and experimental repository conditions. SIA ‘Radon’, Report Res. Cont. N 9744/R0, IAEA, 1998.

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  2. I.A. Sobolev, M.I. Ojovan, O.G. Batyukhnova, N.V. Ojovan and T.D. Scherbatova in Scientific Basis for Nuclear Waste Management, edited by W.J. Gray and I.R. Triay (Mater. Res. Symp. Proc. 465, Pittsburgh, PA 1997), p. 245–252.

  3. M.I. Ojovan, N.V. Ojovan, I.V. Startceva, Z.I. Golubeva, A.S. Barinov in Glass in its disposal environment, editor by P. Van Iseghem, (Book of abstracts Int. Topical Workshop. Bruges, Belgium, 2000) pp. 52–54.

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Authors and Affiliations

  1. Scientific and Industrial Association ‘Radon’, the 7-th Rostovsky Lane 2/14, Moscow, Russia

    M. I. Ojovan, N. V. Ojovan, I. V. Startceva, G. N. Chuikova & A. S. Barinov

Authors
  1. M. I. Ojovan
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  2. N. V. Ojovan
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  3. I. V. Startceva
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  4. G. N. Chuikova
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  5. A. S. Barinov
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Correspondence to M. I. Ojovan.

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Ojovan, M.I., Ojovan, N.V., Startceva, I.V. et al. Simulation of the Waste Glass Behavior in a Loamy Soil of the Wet Repository Site. MRS Online Proceedings Library 663, 837 (2000). https://doi.org/10.1557/PROC-663-837

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  • DOI: https://doi.org/10.1557/PROC-663-837

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