کد مقاله کد نشریه سال انتشار مقاله انگلیسی نسخه تمام متن
1851892 1033843 2006 7 صفحه PDF دانلود رایگان
عنوان انگلیسی مقاله ISI
An investigation of flow characteristics and critical heat flux in vertical upward round tube
موضوعات مرتبط
مهندسی و علوم پایه فیزیک و نجوم فیزیک هسته ای و انرژی بالا
پیش نمایش صفحه اول مقاله
An investigation of flow characteristics and critical heat flux in vertical upward round tube
چکیده انگلیسی
Prediction of critical heat flux (CHF) in annular flow is important for the safety of once-through steam generator and the reactor core under accident conditions. The dryout in annular flow occurs at the point where the film is depleted due to entrainment, deposition, and evaporation. The film thickness, film mass flow rate along axial distribution, and CHF are calculated in vertical upward round tube on the basis of a separated flow model of annular flow. The theoretical CHF values are higher than those derived from experimental data, with error being within 30%.
ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Nuclear Science and Techniques - Volume 17, Issue 3, June 2006, Pages 170-176
نویسندگان
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