A new moving-mesh Finite Volume Method for the efficient solution of two-dimensional neutron diffusion equation using gradient variations of reactor power [PDF]
Nuclear Engineering and Technology, 2019 A new moving-mesh Finite Volume Method (FVM) for the efficient solution of the two-dimensional neutron diffusion equation is introduced. Many other moving-mesh methods developed to solve the neutron diffusion problems use a relatively large number of ...
Mehran Vagheian +2 more
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Integration methods for the time dependent neutron diffusion equation and other approximations of the neutron transport equation [PDF]
, 2020 [ES] Uno de los objetivos más importantes en el análisis de la seguridad en el campo de la ingeniería nuclear es el cálculo, rápido y preciso, de la evolución de la potencia dentro del núcleo del reactor. La distribución de los neutrones se puede describir a través de la ecuación de transporte de Boltzmann.
Amanda María Carreño Sánchez
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Brazilian Journal of Radiation SciencesThis paper explores an approach to accelerate the finite difference method applied to solving the two-dimensional (2D) neutron diffusion equation for two energy groups (2G) independent of time.
Paulo Igor de Oliveira Pessoa +1 more
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Symmetry and separability of the neutron diffusion equation [PDF]
Journal of Physics Communications, 2018 Scott D. Ramsey +3 more
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Development of the SH3-ACNEM Simulator Program in order to Solving the Forward and Adjoint neutron Diffusion Equation for Hexagonal Geometry Reactor Cores [PDF]
مجله علوم و فنون هستهای, 2023 To perform a neutronic analysis of the reactor core, it is necessary to develop nuclear computing software to produce multi-group constants and numerical solutions to the multi-group neutron diffusion equation.
A. Kolali +2 more
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Analytical solution of the multigroup neutron diffusion equation coupled with an iterative method
Brazilian Journal of Radiation Sciences, 2022 Many numerical methods are being used to solve the multigroup neutron diffusion equation for different types of nuclear reactors. These methods solve this equation quite accurately and determine the neutron flux and power distribution in the reactor as ...
Adilson Costa da Silva +3 more
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Neutron Mean Free Path in the Slab Reactor Core using One-Dimensional Multi-group Diffusion Equation
Computational and Experimental Research in Materials and Renewable Energy, 2022 Analysis of the neutron mean free path in the slab reactor core has been carried out using one-dimensional multi-group diffusion equation. This study aims to determine the neutron mean free path in the slab reactor core with the neutron diffusion ...
Putri Nabila +2 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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Solution of neutron-transport multigroup equations system in subcritical systems [PDF]
Nuclear Energy and Technology, 2018 An iteration method has been implemented to solve a neutron transport equation in a multigroup diffusion approximation. A thermoelectric generator containing plutonium dioxide, used as a source of thermal and electric power in spacecraft, was studied.
Igor V. Shamanin +4 more
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A FINITE ELEMENT METHOD FOR NEUTRON NOISE ANALYSIS IN HEXAGONAL REACTORS [PDF]
EPJ Web of Conferences, 2021 The early detection of anomalies through the analysis of the neutron noise recorded by incore and ex-core instrumentation gives the possibility to take proper actions before such problems lead to safety concerns or impact plant availability. The study of
Vidal-Ferràndiz A. +4 more
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