Development of the model to determine the fuel temperature field in a two-dimensional problem statement
Water-cooled water-moderated reactors (VVER) are widely used at Russian nuclear power plants. The VVER reactor core is formed by fuel assemblies consisting of fuel rods. The fuel in fuel rods is uranium dioxide. The safety of the reactor operation is ensured through stringent requi...
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2019-09-01
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doaj-3232e5c4181144bfb4d91ee987494b8a2020-11-25T01:45:13ZengNational Research Nuclear University (MEPhI)Nuclear Energy and Technology2452-30382019-09-015321922410.3897/nucet.5.3931839318Development of the model to determine the fuel temperature field in a two-dimensional problem statementVladimir A. Gorbunov0Natalya B. Ivanova1Nikita A. Lonshakov2Yaroslav V. Belov3Ivanovo State Power UniversityIvanovo State Power UniversityIvanovo State Power UniversityIvanovo State Power University Water-cooled water-moderated reactors (VVER) are widely used at Russian nuclear power plants. The VVER reactor core is formed by fuel assemblies consisting of fuel rods. The fuel in fuel rods is uranium dioxide. The safety of the reactor operation is ensured through stringent requirements for the maximum nuclear fuel temperature. Calculation of temperature fields within the reactor core requires associated problems to be solved to determine the internal energy release in fuel based on neutronic characteristics. Dedicated software for such calculations is not available to a broad range of users. At the present time, there are numerical thermophysical modeling packages available for training or noncommercial applications which are used extensively, including Elcut, Flow Vision, Ansys Fluent, and Comsol Multiphysics. Verification of the obtained results is becoming an important issue in building models using these calculation packages. An analytical solution was obtained as part of the study for the fuel temperature field determination. A program was developed in MathCAD based on this solution. A model was developed in Comsol Multiphysics to determine the fuel temperature field with constant thermophysical properties in a two-dimensional problem statement. The numerical model was verified using the analytical solution. The influence of the number of the grid nodes on the solution accuracy was established. The analytical solution can be used to determine the fuel temperature field at any radial coordinate of the reactor. The temperature field determination model developed in MathCAD can be used to verify numerical models of the fuel temperature field determination developed in dedicated packages. https://nucet.pensoft.net/article/39318/download/pdf/ |
collection |
DOAJ |
language |
English |
format |
Article |
sources |
DOAJ |
author |
Vladimir A. Gorbunov Natalya B. Ivanova Nikita A. Lonshakov Yaroslav V. Belov |
spellingShingle |
Vladimir A. Gorbunov Natalya B. Ivanova Nikita A. Lonshakov Yaroslav V. Belov Development of the model to determine the fuel temperature field in a two-dimensional problem statement Nuclear Energy and Technology |
author_facet |
Vladimir A. Gorbunov Natalya B. Ivanova Nikita A. Lonshakov Yaroslav V. Belov |
author_sort |
Vladimir A. Gorbunov |
title |
Development of the model to determine the fuel temperature field in a two-dimensional problem statement |
title_short |
Development of the model to determine the fuel temperature field in a two-dimensional problem statement |
title_full |
Development of the model to determine the fuel temperature field in a two-dimensional problem statement |
title_fullStr |
Development of the model to determine the fuel temperature field in a two-dimensional problem statement |
title_full_unstemmed |
Development of the model to determine the fuel temperature field in a two-dimensional problem statement |
title_sort |
development of the model to determine the fuel temperature field in a two-dimensional problem statement |
publisher |
National Research Nuclear University (MEPhI) |
series |
Nuclear Energy and Technology |
issn |
2452-3038 |
publishDate |
2019-09-01 |
description |
Water-cooled water-moderated reactors (VVER) are widely used at Russian nuclear power plants. The VVER reactor core is formed by fuel assemblies consisting of fuel rods. The fuel in fuel rods is uranium dioxide. The safety of the reactor operation is ensured through stringent requirements for the maximum nuclear fuel temperature. Calculation of temperature fields within the reactor core requires associated problems to be solved to determine the internal energy release in fuel based on neutronic characteristics. Dedicated software for such calculations is not available to a broad range of users. At the present time, there are numerical thermophysical modeling packages available for training or noncommercial applications which are used extensively, including Elcut, Flow Vision, Ansys Fluent, and Comsol Multiphysics. Verification of the obtained results is becoming an important issue in building models using these calculation packages.
An analytical solution was obtained as part of the study for the fuel temperature field determination. A program was developed in MathCAD based on this solution. A model was developed in Comsol Multiphysics to determine the fuel temperature field with constant thermophysical properties in a two-dimensional problem statement. The numerical model was verified using the analytical solution. The influence of the number of the grid nodes on the solution accuracy was established. The analytical solution can be used to determine the fuel temperature field at any radial coordinate of the reactor. The temperature field determination model developed in MathCAD can be used to verify numerical models of the fuel temperature field determination developed in dedicated packages.
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url |
https://nucet.pensoft.net/article/39318/download/pdf/ |
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