Unstructured Grids and the Multigroup Neutron Diffusion Equation [PDF]
Science and Technology of Nuclear Installations, 2013 The neutron diffusion equation is often used to perform core-level neutronic calculations. It consists of a set of second-order partial differential equations over the spatial coordinates that are, both in the academia and in the industry, usually solved
German Theler
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Application of the smoothed particle hydrodynamics method to the neutron diffusion equation
Nuclear Engineering and TechnologyA novel meshless method, known as Smoothed Particle Hydrodynamics (SPH), is applied to solve the neutron diffusion equation for the first time. The discrete forms for each term of the neutron diffusion equation and the boundary conditions are presented ...
Yiyang Luo +3 more
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Multilevel methods to solve the neutron diffusion equation
Applied Mathematical Modelling, 2001 zbMATH Open Web Interface contents unavailable due to conflicting licenses.
D Ginestar, G Verdú
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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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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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