Results 11 to 20 of about 12,741 (257)
Three-dimensional time-dependent neutron diffusion simulation using average current nodal expansion method [PDF]
Nuclear Technology and Radiation Protection, 2020 In this work, the average current nodal expansion method was developed for the time-dependent neutronic simulation of transients in a nuclear reactor's core.
Valavi Kambiz +2 more
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IMPROVEMENT TO NEM SP3 MODELLING AND SIMULATION [PDF]
EPJ Web of Conferences, 2021 Accurate reactor core steady state safety analysis requires coupling between thermal-hydraulics and three dimensional multigroup pin by pin neutronics.
Xu Yuchao, Hou Jason, Ivanov Kostadin N.
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New 3D Diffusion Code Based on The Nodal Polynomial Expansion
Brazilian Journal of Radiation Sciences, 2021 Nodal Expansion Method (NEM) is widely employed in the neutronic design of nuclear reactors core. The main reason is its higher computational performance and efficiency when compared with the conventional fine mesh difference method or finite element ...
Jadna Mara Santos Mendes +2 more
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Energies, 2021 The Simplified Spherical Harmonic (SPN) approximation was first introduced as a three-dimensional (3D) extension of the plane-geometry Spherical Harmonic (PN) equations.
Yuchao Xu, Jason Hou, Kostadin Ivanov
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Development of nodal diffusion code RAST-V for Vodo–Vodyanoi Energetichesky reactor analysis
Nuclear Engineering and Technology, 2022 This paper presents the development of a nodal diffusion code, RAST-V, and its verification and validation for VVER (vodo–vodyanoi energetichesky reactor) analysis.
Jaerim Jang +2 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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Development of a computer code for neutronic calculations of a hexagonal lattice of nuclear reactor using the flux expansion nodal method [PDF]
Nuclear Technology and Radiation Protection, 2013 The flux expansion nodal method is a suitable method for considering nodalization effects in node corners. In this paper we used this method to solve the intra-nodal flux analytically.
Mohammadnia Meysam +2 more
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EPJ Nuclear Sciences & Technologies, 2019 Coarse mesh nodal methods are widely used in the analysis of nuclear reactors. However, these methods provide only average values of the neutron fluxes.
Neto W.F.P. +3 more
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Yuanzineng kexue jishu, 2022 Hexagonal fuel assemblies are widely used in liquid metal-cooled fast reactors (LMFR). The design and safety analysis of these reactors require three-dimensional full-core coupling calculations of neutron fluxes and currents in the core.
LU Daogang;LYU Siyu;SUI Danting;GUO Jinsong
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Development and Implementation of 3D Algorithm of Neutron Transport Solution Via 2D(MOC) /1D(NEM) Fusion Method [PDF]
Journal of Nuclear Research and ApplicationsProgress in nuclear engineering, as a highly interdisciplinary field, along with evolution in computational software and hardware, gives authorization to 3D transport simulation of highly heterogeneous generation IV reactor cores, instead of 3D diffusion
M. H. Porhemmat, A. Lashkari
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