کد مقاله کد نشریه سال انتشار مقاله انگلیسی نسخه تمام متن
5475018 1521097 2017 6 صفحه PDF دانلود رایگان
عنوان انگلیسی مقاله ISI
Two-dimensional analytical solution for nodal calculation of nuclear reactors
ترجمه فارسی عنوان
راه حل تحلیلی دو بعدی برای محاسبه توزیع راکتورهای هسته ای
کلمات کلیدی
محاسبه گره مش مش درشت تراکم قدرت هسته ای، شار نوترون، راه حل تحلیلی، روش متداول،
موضوعات مرتبط
مهندسی و علوم پایه مهندسی انرژی مهندسی انرژی و فناوری های برق
چکیده انگلیسی
In this paper, the two-dimensional (2D) neutron diffusion equation is analytically solved for two energy groups (2G). The spatial domain of reactor core is divided into a set of nodes with uniform nuclear parameters. To determine iteratively the multiplication factor and the neutron flux in the reactor we combine the analytical solution of the neutron diffusion equation with an iterative method known as power method. The analytical solution for different types of regions that compose the reactor is obtained, such as fuel and reflector regions. Four average fluxes in the node surfaces are used as boundary conditions for analytical solution. Discontinuity factors on the node surfaces derived from the homogenization process are applied to maintain averages reaction rates and the net current in the fuel assembly (FA). To validate the results obtained by the analytical solution a relative power density distribution in the FAs is determined from the neutron flux distribution and compared with the reference values. The results show good accuracy and efficiency.
ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Annals of Nuclear Energy - Volume 100, Part 1, February 2017, Pages 76-81
نویسندگان
, , , ,