کد مقاله کد نشریه سال انتشار مقاله انگلیسی نسخه تمام متن
1568540 999898 2008 9 صفحه PDF دانلود رایگان
عنوان انگلیسی مقاله ISI
Oxidation of aluminum alloy cladding for research and test reactor fuel
موضوعات مرتبط
مهندسی و علوم پایه مهندسی انرژی انرژی هسته ای و مهندسی
پیش نمایش صفحه اول مقاله
Oxidation of aluminum alloy cladding for research and test reactor fuel
چکیده انگلیسی

The oxide thicknesses on aluminum alloy cladding were measured for the test plates from irradiation tests RERTR-6 and 7A in the ATR (advanced test reactor). The measured thicknesses were substantially lower than those of test plates with similar power from other reactors available in the literature. The main reason is believed to be due to the lower pH (pH 5.1–5.3) of the primary coolant water in the ATR than in the other reactors (pH 5.9–6.5) for which we have data. An empirical model for oxide film thickness predictions on aluminum alloy used as fuel cladding in the test reactors was developed as a function of irradiation time, temperature, surface heat flux, pH, and coolant flow rate. The applicable ranges of pH and coolant flow rates cover most research and test reactors. The predictions by the new model are in good agreement with the in-pile test data available in the literature as well as with the RERTR test data measured in the ATR.

ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Journal of Nuclear Materials - Volume 378, Issue 2, 31 August 2008, Pages 220–228
نویسندگان
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