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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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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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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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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Nuclear Engineering and Technology, 2020 A new task of using the Jacobian-Free-Newton-Krylov (JFNK) method for the PWR core transient simulations involving neutronics, thermal hydraulics and mechanics is conducted.
Qingming He +4 more
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Correlations in non-Hermitian systems and diagram techniques for the steady state
Physical Review Research, 2020 I construct a diagrammatic technique for non-Hermitian fermionic systems which allows addressing correlation effects in the steady state by systematic expansion.
Johan Carlström
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Numerical qualification of the GSP3(0) theory using the analytic function expansion nodal method [PDF]
EPJ Web of ConferencesThe simplified P3 (SP3) method is an important way to implement the pin-by-pin neutron transport calculation of the core. This method has the high accuracy but costs twice the computing time of the diffusion method.
Shi Jun +3 more
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Investigation of Nodal Numerical Adjoints From CMFD-Based Acceleration Methods
Frontiers in Energy Research, 2022 In this work, the attribute of mathematical adjoints acquired from various CMFD (coarse-mesh finite difference) accelerated nodal methods based on the nodal expansion method (NEM) is presented.
Taesuk Oh, Yonghee Kim
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