Feasibility study mixed oxide fuel tests in the impulse graphite reactor
The article presents the results of computational studies to substantiate the possibility of testing the fuel of the Multipurpose hYbrid Research Reactor for a High-tech Applications reactor (MYRRHA) in the Impulse Graphite research Reactor (IGR). A scheme for conducting experiments is proposed, whi...
| Main Authors: | , , , , |
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| Format: | Article |
| Language: | English |
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L.N. Gumilyov Eurasian National University
2022-09-01
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| Series: | Eurasian Journal of Physics and Functional Materials |
| Subjects: | |
| Online Access: | https://www.ephys.kz/jour/article/view/324/196 |
| _version_ | 1797985247211552768 |
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| author | G.A. Vityuk V.A. Vityuk A.D. Vurim M.K. Skakov A.V. Gradoboyev |
| author_facet | G.A. Vityuk V.A. Vityuk A.D. Vurim M.K. Skakov A.V. Gradoboyev |
| author_sort | G.A. Vityuk |
| collection | DOAJ |
| description | The article presents the results of computational studies to substantiate the possibility of testing the fuel of the Multipurpose hYbrid Research Reactor for a High-tech Applications reactor (MYRRHA) in the Impulse Graphite research Reactor (IGR). A scheme for conducting experiments is proposed, which allows simulating the operating conditions of MYRRHA fuel elements in a wide range of changes in their thermohydraulic parameters, including the conditions of accidents with the destruction of fuel
pellets, blocking the flow area and stopping the coolant flow. A method for thermohydraulic calculations has been developed, implemented in the software environment of the computational fluid dynamics (CFD) code. A computational model of the experimental device is developed, optimized according to
the spatial partitioning grid. A turbulence model for determining the parameters of convective heat and mass transfer in a eutectic lead-bismuth alloy is selected and substantiated. |
| first_indexed | 2024-04-11T07:15:16Z |
| format | Article |
| id | doaj.art-29e3d9a1b18c46f1a819a90d74e470cb |
| institution | Directory Open Access Journal |
| issn | 2522-9869 2616-8537 |
| language | English |
| last_indexed | 2024-04-11T07:15:16Z |
| publishDate | 2022-09-01 |
| publisher | L.N. Gumilyov Eurasian National University |
| record_format | Article |
| series | Eurasian Journal of Physics and Functional Materials |
| spelling | doaj.art-29e3d9a1b18c46f1a819a90d74e470cb2022-12-22T04:37:59ZengL.N. Gumilyov Eurasian National UniversityEurasian Journal of Physics and Functional Materials2522-98692616-85372022-09-016319821210.32523/ejpfm.2022060305Feasibility study mixed oxide fuel tests in the impulse graphite reactorG.A. Vityuk0V.A. Vityuk1A.D. Vurim2M.K. Skakov3A.V. Gradoboyev4National Nuclear Center of the Republic of Kazakhstan, Kurchatov, KazakhstanNational Nuclear Center of the Republic of Kazakhstan, Kurchatov, KazakhstanNational Nuclear Center of the Republic of Kazakhstan, Kurchatov, KazakhstanNational Nuclear Center of the Republic of Kazakhstan, Kurchatov, KazakhstanTomsk Polytechnic University, Tomsk, RussiaThe article presents the results of computational studies to substantiate the possibility of testing the fuel of the Multipurpose hYbrid Research Reactor for a High-tech Applications reactor (MYRRHA) in the Impulse Graphite research Reactor (IGR). A scheme for conducting experiments is proposed, which allows simulating the operating conditions of MYRRHA fuel elements in a wide range of changes in their thermohydraulic parameters, including the conditions of accidents with the destruction of fuel pellets, blocking the flow area and stopping the coolant flow. A method for thermohydraulic calculations has been developed, implemented in the software environment of the computational fluid dynamics (CFD) code. A computational model of the experimental device is developed, optimized according to the spatial partitioning grid. A turbulence model for determining the parameters of convective heat and mass transfer in a eutectic lead-bismuth alloy is selected and substantiated.https://www.ephys.kz/jour/article/view/324/196myrrha reactor;mixed-oxide fuel;fuel pellet destruction;research impulse graphite reactor;thermohydraulic parameters |
| spellingShingle | G.A. Vityuk V.A. Vityuk A.D. Vurim M.K. Skakov A.V. Gradoboyev Feasibility study mixed oxide fuel tests in the impulse graphite reactor Eurasian Journal of Physics and Functional Materials myrrha reactor; mixed-oxide fuel; fuel pellet destruction; research impulse graphite reactor; thermohydraulic parameters |
| title | Feasibility study mixed oxide fuel tests in the impulse graphite reactor |
| title_full | Feasibility study mixed oxide fuel tests in the impulse graphite reactor |
| title_fullStr | Feasibility study mixed oxide fuel tests in the impulse graphite reactor |
| title_full_unstemmed | Feasibility study mixed oxide fuel tests in the impulse graphite reactor |
| title_short | Feasibility study mixed oxide fuel tests in the impulse graphite reactor |
| title_sort | feasibility study mixed oxide fuel tests in the impulse graphite reactor |
| topic | myrrha reactor; mixed-oxide fuel; fuel pellet destruction; research impulse graphite reactor; thermohydraulic parameters |
| url | https://www.ephys.kz/jour/article/view/324/196 |
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