Published August 1984 | Version v1
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Leaching test of the radioactive glass waste form

  • 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki. Tokai Research Establishment

Description

As a part of the safety evaluation tests of simulated radioactive glass waste forms, the leaching experiments were carried out at 1000C by using the Soxhlet leach test apparatus in hot cell of the Waste Safety Testing Facility(WASTEF). The composition of the glass waste form used for this study is typical of the latest composition. The leach rates of 137Cs and 90Sr were 4.28 x 10-4 g/cm2 day and 1.92 x 10-4 g/cm2 day, respectively. There was little difference between these values and the results of the previous cold tests. The leach rate of 238Pu was 1.82 x 10-6 g/cm2 day. The behavior of leached radionuclides was examined on the basis of the phenomena observed during the leaching experiment. The result implied that the concentration of Pu in the leaching solution was dependent upon the solubility of Pu. (author)

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MF available from INIS under the Report Number.

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Publishing Information

Imprint Pagination
15 p.
Report number
JAERI-M--84-140