A Description of the Mechanistic Dart - Thermal Dispersion Fuel Performance Code and Application to Irradiation Behavior Analysis of U-Mo/Al
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Cited by 5 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. Performance evaluation of thermal conductivity models for fission gases with application to UO2-zirconium dispersion fuel;Annals of Nuclear Energy;2023-06
2. DART Analysis of Irradiation Behavior of U-Mo/Al Dispersion Fuels;Nuclear Technology;2015-07
3. Fission Gas and Bias-Driven Swelling of Nuclear Fuels;Materials Science and Technology;2015-05-11
4. In-pile test results of U-silicide or U-nitride coated U-7Mo particle dispersion fuel in Al;Journal of Nuclear Materials;2014-11
5. A MICROSTRUCTURAL MODEL OF THE THERMAL CONDUCTIVITY OF DISPERSION TYPE FUELS WITH A FUEL MATRIX INTERACTION LAYER;Nuclear Engineering and Technology;2013-12
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