|کد مقاله||کد نشریه||سال انتشار||مقاله انگلیسی||ترجمه فارسی||نسخه تمام متن|
|1727837||1521099||2016||7 صفحه PDF||سفارش دهید||دانلود رایگان|
• The analytic function expansion nodal (AFEN) code, MGHANSP3, was developed.
• MGANSP3 code solves simplified P3 (SP3) equation in hexagonal geometry.
• Two IAEA benchmark problem is used to examine the accuracy of the MGANSP3 code.
In this paper, analytic function expansion nodal (AFEN) method was developed to solve multi-group and multi-dimensional neutron simplified P3 (SP3) equation in reactor cores with hexagonal fuel assembly. In this method, the intranodal fluxes are expanded into a set of analytic basis functions for each group and Legendre moment. Fourteen boundary conditions has been considered that constrain the intranodal flux distributions in the hexagonal-z node, which include twelve radial surface-averaged partial currents and two axial surface-averaged partial currents. The code takes few-groups cross sections produced by a lattice code and calculates the effective multiplication factor (keff), flux in multi-group energy, reactivity, and the relative power density at each fuel assembly. Finally, the solution accuracy is tested for the two and three dimensional IAEA benchmark problem. The 3D IAEA problem has been calculated for three different cases. The numerical results demonstrate that the SP3 AFEN method exhibits better accuracy compared to diffusion method especially when the control materials are inserted in the core.
Journal: Annals of Nuclear Energy - Volume 98, December 2016, Pages 74–80