کد مقاله کد نشریه سال انتشار مقاله انگلیسی نسخه تمام متن
297512 511760 2011 14 صفحه PDF دانلود رایگان
عنوان انگلیسی مقاله ISI
Three-dimensional simulation of a simplified advanced gas-cooled reactor fuel element
موضوعات مرتبط
مهندسی و علوم پایه مهندسی انرژی مهندسی انرژی و فناوری های برق
پیش نمایش صفحه اول مقاله
Three-dimensional simulation of a simplified advanced gas-cooled reactor fuel element
چکیده انگلیسی

The present work involves simulations of a simplified three-dimensional representation of the UK fleet of advanced gas-cooled reactors (AGRs) fuel element using a 30° sector configuration. The computations were carried out using the v2–f formulation which was shown to be one of the most accurate turbulence models in earlier simulations of two-dimensional rib-roughened channels. In the present work main features of the mean flow and heat transfer in the fuel element were identified and discussed. The pressure loss and friction factor were also calculated where good agreement with the experimental correlations was found. Further comparisons were made against simulations of a 2D rib-roughened channel in order to assess the validity and relevance of a ‘2D approximation’ approach. It was shown that although a two-dimensional approach is very useful and economical for ‘parametric studies’, it does not provide an accurate representation of a 3D fuel element configuration, especially for the velocity and pressure coefficient distributions, where large discrepancies were found between the results of the 2D channel and azimuthal planes of the 3D configuration.


► A simplified fuel element of an advanced gas-cooled reactor was simulated using CFD.
► Simulations were undertaken using the v2–f model and a 30° sector geometry.
► Results were presented using velocity, pressure and temperature contours.
► The calculated friction was compared with correlations where good agreement was found.
► Large discrepancies were found when comparing 3D mean profiles with 2D simulations.

ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Nuclear Engineering and Design - Volume 241, Issue 10, October 2011, Pages 4122–4135
نویسندگان
,