Thermomechanical analysis of a lead-cooled fast reactor with a fast-running model
The aim of this work is the development and testing of a simplified and fast-running model for thermomechanical analysis of a Lead-cooled Fast Reactor (LFR). For this work a fast-running mechanical model has been coupled with a heat transfer model previously developed, as part of AZTLAN-platform pro...
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| Format: | Article |
| Language: | English |
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Elsevier
2022-02-01
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| Series: | Case Studies in Thermal Engineering |
| Subjects: | |
| Online Access: | http://www.sciencedirect.com/science/article/pii/S2214157X21008571 |
| _version_ | 1828136699672133632 |
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| author | J. Centeno-Pérez A.D. Pérez-Valseca A. Gómez-Torres R.C. Lopez-Solis A. Vazquez-Rodriguez G. Espinosa-Paredes |
| author_facet | J. Centeno-Pérez A.D. Pérez-Valseca A. Gómez-Torres R.C. Lopez-Solis A. Vazquez-Rodriguez G. Espinosa-Paredes |
| author_sort | J. Centeno-Pérez |
| collection | DOAJ |
| description | The aim of this work is the development and testing of a simplified and fast-running model for thermomechanical analysis of a Lead-cooled Fast Reactor (LFR). For this work a fast-running mechanical model has been coupled with a heat transfer model previously developed, as part of AZTLAN-platform project. In a nuclear reactor, an optimal heat transfer in the fuel is needed to avoid unwanted phenomena related to sudden increases in temperature. One of the main mechanisms of deterioration of heat transfer in the fuel is the thermal expansion of the fuel and cladding since it leads to the narrowing or even blockage of the space between them causing thermal and mechanical loads that can produce fuel failure. Here, the results of the numerical calculation for stress, deformation, and radial displacement in the fuel of an LFR are presented as a function of the temperature. The simplified model was validated with a Finite Element Method peridynamics model getting consistent results. |
| first_indexed | 2024-04-11T18:08:24Z |
| format | Article |
| id | doaj.art-35334c2283b34973a5133fe463323afb |
| institution | Directory Open Access Journal |
| issn | 2214-157X |
| language | English |
| last_indexed | 2024-04-11T18:08:24Z |
| publishDate | 2022-02-01 |
| publisher | Elsevier |
| record_format | Article |
| series | Case Studies in Thermal Engineering |
| spelling | doaj.art-35334c2283b34973a5133fe463323afb2022-12-22T04:10:15ZengElsevierCase Studies in Thermal Engineering2214-157X2022-02-0130101694Thermomechanical analysis of a lead-cooled fast reactor with a fast-running modelJ. Centeno-Pérez0A.D. Pérez-Valseca1A. Gómez-Torres2R.C. Lopez-Solis3A. Vazquez-Rodriguez4G. Espinosa-Paredes5Facultad de Ingeniería, Universidad Nacional Autónoma de México, Facultad de Ingeniería, Mexico City, 04510, MexicoÁrea de Ingeniería en Recursos Energéticos, Universidad Autónoma Metropolitana-Iztapalapa, Mexico City, 09340, MexicoInstituto Nacional de Investigaciones Nucleares, Ocoyoacac, Estado de Mexico, 52750, Mexico; Corresponding author.Instituto Nacional de Investigaciones Nucleares, Ocoyoacac, Estado de Mexico, 52750, MexicoÁrea de Ingeniería en Recursos Energéticos, Universidad Autónoma Metropolitana-Iztapalapa, Mexico City, 09340, MexicoÁrea de Ingeniería en Recursos Energéticos, Universidad Autónoma Metropolitana-Iztapalapa, Mexico City, 09340, MexicoThe aim of this work is the development and testing of a simplified and fast-running model for thermomechanical analysis of a Lead-cooled Fast Reactor (LFR). For this work a fast-running mechanical model has been coupled with a heat transfer model previously developed, as part of AZTLAN-platform project. In a nuclear reactor, an optimal heat transfer in the fuel is needed to avoid unwanted phenomena related to sudden increases in temperature. One of the main mechanisms of deterioration of heat transfer in the fuel is the thermal expansion of the fuel and cladding since it leads to the narrowing or even blockage of the space between them causing thermal and mechanical loads that can produce fuel failure. Here, the results of the numerical calculation for stress, deformation, and radial displacement in the fuel of an LFR are presented as a function of the temperature. The simplified model was validated with a Finite Element Method peridynamics model getting consistent results.http://www.sciencedirect.com/science/article/pii/S2214157X21008571Thermomechanical analysisRadial thermal expansionHeat transfer in nuclear fuel |
| spellingShingle | J. Centeno-Pérez A.D. Pérez-Valseca A. Gómez-Torres R.C. Lopez-Solis A. Vazquez-Rodriguez G. Espinosa-Paredes Thermomechanical analysis of a lead-cooled fast reactor with a fast-running model Case Studies in Thermal Engineering Thermomechanical analysis Radial thermal expansion Heat transfer in nuclear fuel |
| title | Thermomechanical analysis of a lead-cooled fast reactor with a fast-running model |
| title_full | Thermomechanical analysis of a lead-cooled fast reactor with a fast-running model |
| title_fullStr | Thermomechanical analysis of a lead-cooled fast reactor with a fast-running model |
| title_full_unstemmed | Thermomechanical analysis of a lead-cooled fast reactor with a fast-running model |
| title_short | Thermomechanical analysis of a lead-cooled fast reactor with a fast-running model |
| title_sort | thermomechanical analysis of a lead cooled fast reactor with a fast running model |
| topic | Thermomechanical analysis Radial thermal expansion Heat transfer in nuclear fuel |
| url | http://www.sciencedirect.com/science/article/pii/S2214157X21008571 |
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