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    Implementation of a dynamic Monte Carlo method for transients analysis with thermal-hydraulic feedbacks using MCNPX code

    , Article Annals of Nuclear Energy ; Volume 130 , 2019 , Pages 240-249 ; 03064549 (ISSN) Ghaderi Mazaher, M ; Salehi, A. A ; Vosoughi, N ; Sharif University of Technology
    Elsevier Ltd  2019
    Abstract
    Transient analysis which is vital in safety analysis requires a reliable calculation method. Most valid tools use diffusion theory with many approximations by now. However, the Monte Carlo method inherently overcomes these approximations and accurately calculates the parameters of a reactor. In this paper, a new time-dependent transport approach is described to simulate the nuclear reactor dynamic correctly using the MCNPX code. In this approach the fundamental parameters of a nuclear reactor like multiplication factor (K eff ) and mean generation time (t G ) are calculated using MCNPX code. They are then employed in the formulas to compute neutron population, proportional to K eff , during... 

    A new approach for solution of time dependent neutron transport equation based on nodal discretization using MCNPX code with feedback

    , Article Annals of Nuclear Energy ; Volume 133 , 2019 , Pages 519-526 ; 03064549 (ISSN) Ghaderi Mazaher, M ; Salehi, A. A ; Vosoughi, N ; Sharif University of Technology
    Elsevier Ltd  2019
    Abstract
    This paper proposes a new method for solving the time-dependent neutron transport equation based on nodal discretization using the MCNPX code. Most valid nodal codes are based on the diffusion theory with differences in approximating the leakage term until now. However, the Monte Carlo (MC) method is able to estimate transport parameters without approximations usual in diffusion method. Therefore, improving the nodal approach via the MC techniques can substantially reduce the errors caused by diffusion approximations. In the proposed method, the reactor core is divided into nodes of arbitrary dimensions, and all terms of the transport equation e.g. interaction rates and leakage ratio are... 

    Monte carlo modeling of magnification mode for quantitative assessment of image quality in mammography systems

    , Article 2019 IEEE International Symposium on Medical Measurements and Applications, MeMeA 2019, 26 June 2019 through 28 June 2019 ; 2019 ; 9781538684276 (ISBN) Safarzadeh Amiri, A ; Khodajou Chokami, H ; Vosoughi, N ; Noorvand, M ; IEEE; IEEE Instrumentation and Measurement Society; Kadir Has University (KHU); UME ; Sharif University of Technology
    Institute of Electrical and Electronics Engineers Inc  2019
    Abstract
    Scattered radiations are one of the most important factors in the degradation of the image quality of mammography systems. Some techniques have been proposed for the reduction of such rays. Magnification mode can be done by increasing the air gap which determined by the distance of the breast and image intensifier. It is one of the useful techniques to elevate the produced image quality due to the rejection of scattered photons. Monte Carlo N-Particle eXtended transport code (MCNPX) version 2.7.0 is a software package for the simulation of physical processes. In this work, this computer code is used for analyzing the effects of magnification mode on mammographic image quality. To this...