Autor: |
Asmolov, V. G., Zagryazkin, V. N., Astakhova, E. V., Vishnevskii, V. Yu., D'yakov, E. K. |
Předmět: |
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Zdroj: |
High Temperature; Mar/Apr2004, Vol. 42 Issue 2, p242-251, 10p |
Abstrakt: |
This paper is devoted to the study into the structure of core melts of reactors such as water-moderated water-cooled power reactors. The quenching method is used to experimentally investigate the structure of U-Zr- O melts with an atomic ratio of U/Zr = 1.2–1.6 at a temperature of 2773 K. It is found that, for the most probable compositions of U-Zr-O melts under conditions of heavy accident with the Zr oxidation level above 30%, no separation of the corium melt into immiscible liquids is observed. [ABSTRACT FROM AUTHOR] |
Databáze: |
Complementary Index |
Externí odkaz: |
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