The effect of errors in the neutron flux density on the uncertainties of nuclear concentrations of nuclides arising during the calculation of fuel burnup in cells with different neutron spectra

Computational studies have been carried out showing the complex time dependence of uncertainties in nuclear concentrations of various nuclides arising from the propagation of the neutron flux density errors in the burnup calculation process in cells with different neutron spectra on the above errors...

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Main Authors: Aleksandr N. Pisarev, Valery V. Kolesov, Dmitry V. Kolesov
Format: Article
Language:English
Published: National Research Nuclear University (MEPhI) 2022-12-01
Series:Nuclear Energy and Technology
Subjects:
Online Access:https://nucet.pensoft.net/article/96559/download/pdf/
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author Aleksandr N. Pisarev
Valery V. Kolesov
Dmitry V. Kolesov
author_facet Aleksandr N. Pisarev
Valery V. Kolesov
Dmitry V. Kolesov
author_sort Aleksandr N. Pisarev
collection DOAJ
description Computational studies have been carried out showing the complex time dependence of uncertainties in nuclear concentrations of various nuclides arising from the propagation of the neutron flux density errors in the burnup calculation process in cells with different neutron spectra on the above errors. It is found that these uncertainties not only depend on the burnup time in a complex way, but also depend on the spectrum of the cell. The variants of the cell with thermal and fast neutron spectra were considered. The calculations were performed using the VisualBurnOut program (Kolesov et al. 2009), which makes it possible to estimate these uncertainties arising due to errors in the input parameters of the burnup problem (reaction rates, neutron flux density, etc.). The influence of the number of calculated burnup points on the results of burnup calculations by the Monte Carlo method was investigated. Uncertainties arising in nuclear concentrations at intermediate calculation steps due to errors in nuclear concentrations appearing at the previous step were taken into account in the calculations.
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spelling doaj.art-20051143fa1447d79441295df3b300a02022-12-22T03:54:10ZengNational Research Nuclear University (MEPhI)Nuclear Energy and Technology2452-30382022-12-018423123510.3897/nucet.8.9655996559The effect of errors in the neutron flux density on the uncertainties of nuclear concentrations of nuclides arising during the calculation of fuel burnup in cells with different neutron spectraAleksandr N. Pisarev0Valery V. Kolesov1Dmitry V. Kolesov2National Research Center “Kurchatov Institute”National Research Center “Kurchatov Institute”FSBSI “Research Institute of General Pathology and Pathophysiology”Computational studies have been carried out showing the complex time dependence of uncertainties in nuclear concentrations of various nuclides arising from the propagation of the neutron flux density errors in the burnup calculation process in cells with different neutron spectra on the above errors. It is found that these uncertainties not only depend on the burnup time in a complex way, but also depend on the spectrum of the cell. The variants of the cell with thermal and fast neutron spectra were considered. The calculations were performed using the VisualBurnOut program (Kolesov et al. 2009), which makes it possible to estimate these uncertainties arising due to errors in the input parameters of the burnup problem (reaction rates, neutron flux density, etc.). The influence of the number of calculated burnup points on the results of burnup calculations by the Monte Carlo method was investigated. Uncertainties arising in nuclear concentrations at intermediate calculation steps due to errors in nuclear concentrations appearing at the previous step were taken into account in the calculations.https://nucet.pensoft.net/article/96559/download/pdf/Reactor plantburnup calculations
spellingShingle Aleksandr N. Pisarev
Valery V. Kolesov
Dmitry V. Kolesov
The effect of errors in the neutron flux density on the uncertainties of nuclear concentrations of nuclides arising during the calculation of fuel burnup in cells with different neutron spectra
Nuclear Energy and Technology
Reactor plant
burnup calculations
title The effect of errors in the neutron flux density on the uncertainties of nuclear concentrations of nuclides arising during the calculation of fuel burnup in cells with different neutron spectra
title_full The effect of errors in the neutron flux density on the uncertainties of nuclear concentrations of nuclides arising during the calculation of fuel burnup in cells with different neutron spectra
title_fullStr The effect of errors in the neutron flux density on the uncertainties of nuclear concentrations of nuclides arising during the calculation of fuel burnup in cells with different neutron spectra
title_full_unstemmed The effect of errors in the neutron flux density on the uncertainties of nuclear concentrations of nuclides arising during the calculation of fuel burnup in cells with different neutron spectra
title_short The effect of errors in the neutron flux density on the uncertainties of nuclear concentrations of nuclides arising during the calculation of fuel burnup in cells with different neutron spectra
title_sort the effect of errors in the neutron flux density on the uncertainties of nuclear concentrations of nuclides arising during the calculation of fuel burnup in cells with different neutron spectra
topic Reactor plant
burnup calculations
url https://nucet.pensoft.net/article/96559/download/pdf/
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