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Abstract <p>Radioactive specimens of borosilicate glasses containing HLW short-lived fraction from the raffinate of the first extraction cycle of SNF reprocessing were fabricated at the hot cell vitrification unit of the radiochemical plant. The glasses were identical in their chemical composition but differed in the content of the cesium–strontium fraction. The proportion of radioactive isotopes in the specimens of each glass composition corresponded to the specified heat generation rates of 1, 15, 25, and 35 kW/m<sup>3</sup>, while the waste form specific activity ranged from 150 to 4600 Ci/kg. Chemical durability of the radioactive glass specimens was tested. The cesium and strontium leaching rates did not exceed 1 × 10<sup>–4</sup> g/(cm<sup>2</sup> day) at any point of the run.</p>

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Synthesis and Study of Radioactive Specimens of Borosilicate Glasses with Different Content of Cesium–Strontium Fraction

  • 期刊论文

  • 发表日期：

    2025年8月1日

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  • A. Yu. Nikulina,
  • E. V. Braichun,
  • E. V. Polyakov,
  • M. B. Remizov,
  • P. V. Kozlov,
  • A. S. Levunin

摘要

Abstract

Radioactive specimens of borosilicate glasses containing HLW short-lived fraction from the raffinate of the first extraction cycle of SNF reprocessing were fabricated at the hot cell vitrification unit of the radiochemical plant. The glasses were identical in their chemical composition but differed in the content of the cesium–strontium fraction. The proportion of radioactive isotopes in the specimens of each glass composition corresponded to the specified heat generation rates of 1, 15, 25, and 35 kW/m3, while the waste form specific activity ranged from 150 to 4600 Ci/kg. Chemical durability of the radioactive glass specimens was tested. The cesium and strontium leaching rates did not exceed 1 × 10–4 g/(cm2 day) at any point of the run.