Static Leaching of Radioactive Glass Under Conditions Simulating a Granitic Repository for High-Level Waste: Phase 1.

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<jats:title>ABSTRACT</jats:title><jats:p>A joint research project with participation from Japan, Switzerland and Sweden is underway at Studsvik (The JSS-project). The project concerns investigations on the leaching of fully radioactive glass (containing 12 wt% fission product oxides and actinide oxides) manufactured by CEA/Marcoule.</jats:p><jats:p>So far the glass has been leached in doubly distilled water and in silicate water at 90°C. Some leaching experiments involved the presence of crushed Stripa granite in the same containers as the glass.</jats:p><jats:p>Due to strong radiation and the presence of plutonium the leaching was carried out in a specially designed lead cave using gilded stainless steel containers.</jats:p><jats:p>Weight losses, pH and elemental mass losses were determined together with infrared reflection spectral changes. These data are compared to those obtained from a simulated nonradioactive glass of nearly the same composition and to similar alkali borosilicate glasses previously investigated at Studsvik.</jats:p>

収録刊行物

  • MRS Proceedings

    MRS Proceedings 26 1983-01-01

    Springer Science and Business Media LLC

詳細情報 詳細情報について

  • CRID
    1873679867442497792
  • DOI
    10.1557/proc-26-671
  • ISSN
    19464274
    02729172
  • データソース種別
    • OpenAIRE

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