Second order of average current nodal expansion method for the neutron noise simulation

The aim of this work is to prepare a neutron noise calculator based on the second order of average current nodal expansion method (ACNEM). Generally, nodal methods have the ability to fulfill the neutronic analysis with adequate precision using coarse meshes as large as a fuel assembly size. But, fo...

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Main Authors: N. Poursalehi, A. Abed
Format: Article
Language:English
Published: Elsevier 2021-05-01
Series:Nuclear Engineering and Technology
Subjects:
Online Access:http://www.sciencedirect.com/science/article/pii/S1738573320309189
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spelling doaj-a631d704f2a34d9ba612bc1fdf3cbb0e2021-04-24T05:56:40ZengElsevierNuclear Engineering and Technology1738-57332021-05-0153513911402Second order of average current nodal expansion method for the neutron noise simulationN. Poursalehi0A. Abed1Department of Engineering, Central Tehran Branch, Islamic Azad University, Tehran, Iran; Corresponding author.School of Energy & Power Engineering, National Research Tomsk Polytechnic University, Tomsk, RussiaThe aim of this work is to prepare a neutron noise calculator based on the second order of average current nodal expansion method (ACNEM). Generally, nodal methods have the ability to fulfill the neutronic analysis with adequate precision using coarse meshes as large as a fuel assembly size. But, for the zeroth order of ACNEM, the accuracy of neutronic simulations may not be sufficient when coarse meshes are employed in the reactor core modeling. In this work, the capability of second order ACNEM is extended for solving the neutron diffusion equation in the frequency domain using coarse meshes. For this purpose, two problems are modeled and checked including a slab reactor and 2D BIBLIS PWR. For validating of results, a semi-analytical solution is utilized for 1D test case, and for 2D problem, the results of both forward and adjoint neutron noise calculations are exploited. Numerical results indicate that by increasing the order of method, the errors of frequency dependent coarse mesh solutions are considerably decreased in comparison to the reference. Accordingly, the accuracy of second order ACNEM can be acceptable for the neutron noise calculations by using coarse meshes in the nuclear reactor core.http://www.sciencedirect.com/science/article/pii/S1738573320309189Frequency dependent diffusion equationNeutron noiseAverage current nodal expansion approachSecond order of solution
collection DOAJ
language English
format Article
sources DOAJ
author N. Poursalehi
A. Abed
spellingShingle N. Poursalehi
A. Abed
Second order of average current nodal expansion method for the neutron noise simulation
Nuclear Engineering and Technology
Frequency dependent diffusion equation
Neutron noise
Average current nodal expansion approach
Second order of solution
author_facet N. Poursalehi
A. Abed
author_sort N. Poursalehi
title Second order of average current nodal expansion method for the neutron noise simulation
title_short Second order of average current nodal expansion method for the neutron noise simulation
title_full Second order of average current nodal expansion method for the neutron noise simulation
title_fullStr Second order of average current nodal expansion method for the neutron noise simulation
title_full_unstemmed Second order of average current nodal expansion method for the neutron noise simulation
title_sort second order of average current nodal expansion method for the neutron noise simulation
publisher Elsevier
series Nuclear Engineering and Technology
issn 1738-5733
publishDate 2021-05-01
description The aim of this work is to prepare a neutron noise calculator based on the second order of average current nodal expansion method (ACNEM). Generally, nodal methods have the ability to fulfill the neutronic analysis with adequate precision using coarse meshes as large as a fuel assembly size. But, for the zeroth order of ACNEM, the accuracy of neutronic simulations may not be sufficient when coarse meshes are employed in the reactor core modeling. In this work, the capability of second order ACNEM is extended for solving the neutron diffusion equation in the frequency domain using coarse meshes. For this purpose, two problems are modeled and checked including a slab reactor and 2D BIBLIS PWR. For validating of results, a semi-analytical solution is utilized for 1D test case, and for 2D problem, the results of both forward and adjoint neutron noise calculations are exploited. Numerical results indicate that by increasing the order of method, the errors of frequency dependent coarse mesh solutions are considerably decreased in comparison to the reference. Accordingly, the accuracy of second order ACNEM can be acceptable for the neutron noise calculations by using coarse meshes in the nuclear reactor core.
topic Frequency dependent diffusion equation
Neutron noise
Average current nodal expansion approach
Second order of solution
url http://www.sciencedirect.com/science/article/pii/S1738573320309189
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