Vitrification of a Simulator of Vat Residues from Liquid Radioactive Waste-Reference-Cited by-同舟云学术

Vitrification of a Simulator of Vat Residues from Liquid Radioactive Waste

Published:2023-03-02 Issue:1 Volume: Page:94-101
ISSN:2312-4539
Container-title:East European Journal of Physics
language:
Short-container-title:East Eur. J. Phys.

Author:

Sayenko Sergii^ORCID,Shkuropatenko Volodymyr^ORCID,Svitlychnyi Yevhenii^ORCID,Zykova Anna^ORCID,Karsim Svitlana^ORCID,Kutnii Dmytro^ORCID,Morgunov Volodymyr^ORCID

Abstract

The study on the posibility of the use of the optimal glass compositions for vitrification of an imitator of vat residues of liquid radioactive waste from nuclear power plants with VVER-1000 reactors was carried out. The main process parameters such as vitrification temperature, strength, corrosion resistance, absence of crystalline phases, minimization of glass-forming additives and inclusion the maximum amount of waste were analyzed. It has been established that the melting temperature of lead-borosilicate glass matrices was 1150 °C, which satisfies the requirements for vitrification of low- and medium-level waste. The ultimate compressive strength of the obtained samples of glass matrices was 136.0 MPa. In addition, it has been shown that lead-borosilicate glass matrices are the most resistant to leaching. The cesium leaching rate was 1.5·10-5 g/cm2·day.

Publisher

V. N. Karazin Kharkiv National University

Subject

General Physics and Astronomy,General Materials Science

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