Results 11 to 20 of about 6,219 (301)
EPJ Web of Conferences, 2016 Eigenvalues are obtained for one-dimensional steady-state neutron transport equation in slab geometry using Henyey-Greenstein (HG) phase function. Firstly, HG phase function is inserted into neutron transport equation then eigenvalues are calculated for ...
Bülbül Ahmet
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Diffusion Approximation to Neutron Transport Equation with First Kind of Chebyshev Polynomials
Süleyman Demirel Üniversitesi Fen-Edebiyat Fakültesi Fen Dergisi, 2015 : The first kind of Chebyshev polynomials are used for the series expansion of the neutron angular flux in neutron transport theory. The first order approximation known as the diffusion approximation is applied to one-dimensional neutron transport ...
Ökkeş EGE +2 more
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Solution methods of neutron transport equation in nuclear reactors
Jurnal Ilmu Dasar, 2013 A few numerical methods that usually used to solve neutron transport equation in nuclear reactor are SN dan PN method, Monte Carlo, Collision Probability and Methods of Characteristics . First two methods have been developed using diffusion approach, and
Mohamad Ali Shafii
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A ROBUST SECOND-ORDER MULTIPLE BALANCE METHOD FOR TIME-DEPENDENT NEUTRON TRANSPORT SIMULATIONS [PDF]
EPJ Web of Conferences, 2021 A second-order “Time-Dependent Multiple Balance” (TDMB) method for solving neutron transport problems is introduced and investigated. TDMB consists of solving two coupled equations: (i) the original balance equation (the transport equation integrated ...
Variansyah Ilham +2 more
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Brazilian Journal of Radiation Sciences, 2021 This work proposes to implement the cell calculation considering the fuel burning using the WIMSD-5B code. The cell calculation procedure allows determining the nuclear parameters present in the multi-group neutron diffusion equation and for this purpose
Desirée Yael de Sena Tavares +2 more
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Brazilian Journal of Radiation Sciences, 2023 In this article, we present an application of the coarse-mesh Deterministic Spectral Method (SDM) to generate multigroup angular fluxes in one-dimensional spatial domains using the neutron transport stationary equation, in the formulation of discrete ...
F. T. C. S. Balbina +2 more
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Multi-species Neutron Transport Equation [PDF]
Journal of Statistical Physics, 2019 The Neutron Transport Equation (NTE) describes the flux of neutrons through inhomogeneous fissile medium. Whilst well treated in the nuclear physics literature (cf. [9, 27]), the NTE has had a somewhat scattered treatment in mathematical literature with a variety of different approaches (cf. [8, 25]).
Alexander M. G. Cox +3 more
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Nuclear Engineering and Technology, 2020 The telegrapher's theory was used to develop a new formulation for the neutron noise equation. Telegrapher's equation is supposed to demonstrate a more realistic approximation for neutron transport phenomena, especially in comparison to the diffusion ...
Mona Bahrami, Naser Vosoughi
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Direct discrete method and its application to neutron transport problems [PDF]
Nuclear Technology and Radiation Protection, 2003 The objective of this paper is to introduce a new direct method for neutronic calculations. This method, called direct discrete method, is simpler than the application of the neutron transport equation and more compatible with the physical meanings of ...
Vosoughi Naser +3 more
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Analysis of Kobayashi benchmark with indigenous Monte Carlo neutron transport code PATMOC
Physics Open, 2023 The solution of the neutron transport equation is the basic input for the reactor physics design of a nuclear reactor system. Because of the complexities of geometry and cross-section data, the neutron transport equation is generally solved using ...
Amod Kishore Mallick, Umasankari Kannan
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