Simulation of the kinetics of the UO2 dissolution by molten Zircaloy-4 between 1950 and 2250°C-Reference-Cited by-同舟云学术

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Simulation of the kinetics of the UO2 dissolution by molten Zircaloy-4 between 1950 and 2250°C

Published:1988-08 Issue: Volume:158 Page:143-158
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Wilhelm Aida N.,García Eduarde A.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference9 articles.

1. Mechanisches und chemisches Verhalten von Zircaloy-Hüllrohren und UO2-Brennstoff bei hohen Temperaturen;Hofmann,1986

2. PWR fuel element behavior at temperatures up to 2350°C;Hagen,1986

3. Chemical Interactions Between UO2 and Zircaloy-4 from 1000 to 2000°C

4. Physical and chemical phenomena associated with the dissolution of solid UO2 by molten Zircaloy-4;Hofmann;ASTM-STP 824,1984

5. Chemical interactions of solid and liquid Zircaloy-4 with UO2 under transient nonoxidizing conditions;Hofmann,1983

Cited by 11 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Thermodynamic approach for determination of fuel relocation condition in severe accident progression;Journal of Nuclear Materials;2020-02

2. Distributions of density and fission products in the reaction product between irradiated MOX fuel and molten zircaloy-2;Journal of Nuclear Science and Technology;2017-08-22

3. Effects of interaction between molten zircaloy and irradiated MOX fuel on the fission product release behavior;Journal of Nuclear Science and Technology;2014-03-12

4. Fission product release mechanisms during reactor accident conditions;Journal of Nuclear Materials;1999-04

5. Critical evaluation of uranium oxide dissolution by molten Zircaloy in different crucible tests;Journal of Nuclear Materials;1996-07

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