کد مقاله کد نشریه سال انتشار مقاله انگلیسی نسخه تمام متن
7963303 1514143 2018 10 صفحه PDF دانلود رایگان
عنوان انگلیسی مقاله ISI
Thermal conductivity of fresh and irradiated U-Mo fuels
موضوعات مرتبط
مهندسی و علوم پایه مهندسی انرژی انرژی هسته ای و مهندسی
پیش نمایش صفحه اول مقاله
Thermal conductivity of fresh and irradiated U-Mo fuels
چکیده انگلیسی
The difference of decrease for both fuels originates from effects in the matrix that occur during irradiation, like for dispersion fuel the gradual disappearance of the Al matrix with increased burn-up and the subsequent growth of an interaction layer (IDL) between the U-Mo fuel particle and Al matrix and subsequent matrix hardening. The growth of fission gas bubbles and the decomposition of the U-Mo crystal lattice also affect both dispersion and monolithic fuel.
ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Journal of Nuclear Materials - Volume 503, May 2018, Pages 304-313
نویسندگان
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