Vitrification of Chloride Wastes in the Pyroelectrochemical Method of Reprocessing Irradiated Nuclear Fuel

被引：0

作者：

Yu. G. Lavrinovich

M. V. Kormilitsyn

V. I. Konovalov

I. V. Tselishchev

S. V. Tomilin

V. M. Chistyakov

机构：

[1] State Science Center of the Russian Federation – Scientific-Research Institute of Nuclear Reactors,Federal State Unitary Enterprise

来源：

Atomic Energy | 2003年 / 95卷

关键词：

Chloride; Thermal Resistance; Real Sample; Nuclear Fuel; Glass Matrix;

D O I：

暂无

中图分类号：

学科分类号：

摘要：

The results of investigations of the vitrification of chloride wastes produced during test reprocessing of spent BOR-60 fuel by the pyroelectrochemical method are presented. A method is proposed for converting chlorides into metaphosphates beforehand, which makes it possible to introduce up to 46% wastes into the glass matrix. The optimal composition of the glass matrix is determined, and the properties of the model and real samples obtained are presented. The hydrolytic and thermal resistance of the samples is investigated.

引用

页码：781 / 785

页数：4

共 14 条

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[5]

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