| Autor: |
Ustinov, O. A., Yakunin, S. A. |
| Předmět: |
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| Zdroj: |
Radiochemistry; Aug2021, Vol. 63 Issue 4, p395-400, 6p |
| Abstrakt: |
With regard to the radioactive waste vitrification technology, literature data on the behavior of technetium and its release into the gas phase are reviewed. In various types of spent nuclear fuel (SNF), the content of technetium varies from 16 to 1350 g per 1 ton of SNF. In nitric acid solutions, technetium exists mainly in the form of pertechnetate anions TcO4– and, when heated, is released into the gas phase in the form of Тс2О7 and НТсО4. The volatility of technetium during vitrification varies from fractions of a percent to 70%. Two directions of technological solutions for capturing technetium from the gas phase are described: low-temperature methods using liquid-type apparatus and high-temperature methods with capturing onto zeolite and aluminosilicate filters. [ABSTRACT FROM AUTHOR] |
| Databáze: |
Complementary Index |
| Externí odkaz: |
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