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Home Archive of journals 2024, 2 (27) Demonstration Research of Glass Matrix for Solidified Radioactive Waste

DEMONSTRATION RESEARCH OF GLASS MATRIX FOR SOLIDIFIED RADIOACTIVE WASTE

JOURNAL: 2024, 2 (27), p. 38-49

AUTHORS: E.A. Kinev, N.V. Glushkova, V.I. Pastukhov, V.A. Tsygvintsev, M.V. Evseev, O.I. Asiptsov, R.P. Karagergi, K.M. Ladeyshikov, P.V. Kozlov, E.A. Belanova, M.B. Remizov

ANNOTATION:

The paper discusses the instrumentation installed in protective chambers and the methodological refinement of materials science research focused on model radioactive waste (RW) immobilized into an aluminophosphate waste form. The paper considers remote sample preparation and actual research launched in the IRM’s protective chambers to study model glass materials. The study provided basic characteristics of glass matrices (density, mechanical and elastic properties, thermal resistance, phase and elemental compositions) that were required to compare them with actual characteristics of solidified liquid radioactive waste produced by FSUE PA Mayak based on aluminophosphate glass after its long-term container storage.

Keywords: aluminophosphate glass, mechanical and elastic properties, structure, microhardness, density, composition, devitrification, radioactive waste.


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Kinev . ., Glushkova N. V., Pastukhov V. I., Tsigvintsev V. ., Evseev . V., Asiptsov . I., Karagergi R. P., Ladeyshikov . M., Kozlov P. V., Polyakov . V., Remizov M. B., Belanova E. A. Demonstration research of glass matrix for solidified radioactive waste. Radioactive Waste, 2024, no. 2 (27), pp. 38—49. DOI: 10.25283/2587- 9707-2024-2-38-49. (In Russian).


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