Comparison of methods for calculating the neutronic characteristics of a VVER-1200 fuel assembly

This article presents the results of neutronic calculations of a VVER-1200 fuel assembly carried out using the multi-purpose three-dimensional continuous-energy Monte Carlo particle transport code Serpent 2. The study compares neutronic characteristics during the fuel burnup process (1) with and (2)...

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Main Authors: Aleksey V. Lavronenko, Vyacheslav G. Savankov, Ruslan A. Vnukov, Elena A. Chistozvonova
Format: Article
Language:English
Published: National Research Nuclear University (MEPhI) 2022-09-01
Series:Nuclear Energy and Technology
Subjects:
Online Access:https://nucet.pensoft.net/article/93894/download/pdf/
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author Aleksey V. Lavronenko
Vyacheslav G. Savankov
Ruslan A. Vnukov
Elena A. Chistozvonova
author_facet Aleksey V. Lavronenko
Vyacheslav G. Savankov
Ruslan A. Vnukov
Elena A. Chistozvonova
author_sort Aleksey V. Lavronenko
collection DOAJ
description This article presents the results of neutronic calculations of a VVER-1200 fuel assembly carried out using the multi-purpose three-dimensional continuous-energy Monte Carlo particle transport code Serpent 2. The study compares neutronic characteristics during the fuel burnup process (1) with and (2) without fuel cooling. In the first option, the FA fuel campaign was simulated with 30-day cooling periods between reactor campaigns. The second option assumed simulating the FA fuel campaign without fuel cooling. In the course of the study, the authors determined the infinite neutron multiplication factors as well as the fuel burnup dependence of the concentrations of xenon, samarium and gadolinium nuclides. In addition, it should be noted that no differences were found in the change in the concentration of gadolinium isotopes, the discrepancy in the values of the multiplication factor, and the accumulation of samarium isotopes during the campaign.
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spelling doaj.art-0a5ddb64bd604d798eb8af0ca01fa3eb2022-12-22T04:26:41ZengNational Research Nuclear University (MEPhI)Nuclear Energy and Technology2452-30382022-09-018316116510.3897/nucet.8.9389493894Comparison of methods for calculating the neutronic characteristics of a VVER-1200 fuel assemblyAleksey V. Lavronenko0Vyacheslav G. Savankov1Ruslan A. Vnukov2Elena A. Chistozvonova3Obninsk Institute for Nuclear Power Engineering NRNU MEPhIObninsk Institute for Nuclear Power Engineering NRNU MEPhIObninsk Institute for Nuclear Power Engineering NRNU MEPhIObninsk Institute for Nuclear Power Engineering NRNU MEPhIThis article presents the results of neutronic calculations of a VVER-1200 fuel assembly carried out using the multi-purpose three-dimensional continuous-energy Monte Carlo particle transport code Serpent 2. The study compares neutronic characteristics during the fuel burnup process (1) with and (2) without fuel cooling. In the first option, the FA fuel campaign was simulated with 30-day cooling periods between reactor campaigns. The second option assumed simulating the FA fuel campaign without fuel cooling. In the course of the study, the authors determined the infinite neutron multiplication factors as well as the fuel burnup dependence of the concentrations of xenon, samarium and gadolinium nuclides. In addition, it should be noted that no differences were found in the change in the concentration of gadolinium isotopes, the discrepancy in the values of the multiplication factor, and the accumulation of samarium isotopes during the campaign.https://nucet.pensoft.net/article/93894/download/pdf/Fuel assembly (FA)neutronic char
spellingShingle Aleksey V. Lavronenko
Vyacheslav G. Savankov
Ruslan A. Vnukov
Elena A. Chistozvonova
Comparison of methods for calculating the neutronic characteristics of a VVER-1200 fuel assembly
Nuclear Energy and Technology
Fuel assembly (FA)
neutronic char
title Comparison of methods for calculating the neutronic characteristics of a VVER-1200 fuel assembly
title_full Comparison of methods for calculating the neutronic characteristics of a VVER-1200 fuel assembly
title_fullStr Comparison of methods for calculating the neutronic characteristics of a VVER-1200 fuel assembly
title_full_unstemmed Comparison of methods for calculating the neutronic characteristics of a VVER-1200 fuel assembly
title_short Comparison of methods for calculating the neutronic characteristics of a VVER-1200 fuel assembly
title_sort comparison of methods for calculating the neutronic characteristics of a vver 1200 fuel assembly
topic Fuel assembly (FA)
neutronic char
url https://nucet.pensoft.net/article/93894/download/pdf/
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