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    Enhanced finite difference scheme for the neutron diffusion equation using the importance function

    , Article Annals of Nuclear Energy ; Volume 96 , 2016 , Pages 412-421 ; 03064549 (ISSN) Vagheian, M ; Vosoughi, N ; Gharib, M ; Sharif University of Technology
    Elsevier Ltd  2016
    Abstract
    Mesh point positions in Finite Difference Method (FDM) of discretization for the neutron diffusion equation can remarkably affect the averaged neutron fluxes as well as the effective multiplication factor. In this study, by aid of improving the mesh point positions, an enhanced finite difference scheme for the neutron diffusion equation is proposed based on the neutron importance function. In order to determine the neutron importance function, the adjoint (backward) neutron diffusion calculations are performed in the same procedure as for the forward calculations. Considering the neutron importance function, the mesh points can be improved through the entire reactor core. Accordingly, in... 

    Numerical solution of the neutron transport equation using cellular neural networks

    , Article Annals of Nuclear Energy ; Volume 36, Issue 1 , 2009 , Pages 15-27 ; 03064549 (ISSN) Boroushaki, M ; Sharif University of Technology
    2009
    Abstract
    Various methods have been used for solving the neutron transport equation in the past, and a number of computer codes have been developed based on these solution methods. This paper describes a novel method for the solution of the steady-state and time-dependent neutron transport equation using the duality between neutronic parameters in the method of characteristic (MOC) and the electrical parameters in the cellular neural networks (CNN). The relevant electrical circuit can be simulated by professional electrical circuit simulator software, HSPICE. This software is used for numerical solution of the transport equation only by preparation of appropriate inputs. This method does not need...