A Coupled Calculation Suite for Atucha II Operational Transients Analysis
While more than a decade ago reactor and thermal hydraulic calculations were tedious and often needed a lot of approximations and simplifications that forced the designers to take a very conservative approach, computational resources available nowadays allow engineers to cope with increasingly compl...
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| Main Authors: | , , , , , |
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| Format: | Article |
| Language: | English |
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Wiley
2011-01-01
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| Series: | Science and Technology of Nuclear Installations |
| Online Access: | http://dx.doi.org/10.1155/2011/785304 |
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| author | Oscar Mazzantini Miguel Schivo Julián Di Césare Ricardo Garbero Matías Rivero Germán Theler |
| author_facet | Oscar Mazzantini Miguel Schivo Julián Di Césare Ricardo Garbero Matías Rivero Germán Theler |
| author_sort | Oscar Mazzantini |
| collection | DOAJ |
| description | While more than a decade ago reactor and thermal hydraulic calculations were tedious and often needed a lot of approximations and simplifications that forced the designers to take a very conservative approach, computational resources available nowadays allow engineers to cope with increasingly complex problems in a reasonable time. The use of best-estimate calculations provides tools to justify convenient engineering margins, reduces costs, and maximises economic benefits. In this direction, a suite of coupled best-estimate specific calculation codes was developed to analyse the behaviour of the Atucha II nuclear power plant in Argentina. The developed tool includes three-dimensional spatial neutron kinetics, a channel-level model of the core thermal hydraulics with subcooled boiling correlations, a one-dimensional model of the primary and secondary circuits including pumps, steam generators, heat exchangers, and the turbine with all their associated control loops, and a complete simulation of the reactor control, limitation, and protection system working in closed-loop conditions as a faithful representation of the real power plant. In the present paper, a description of the coupling scheme between the codes involved is given, and some examples of their application to Atucha II are shown. |
| format | Article |
| id | doaj-art-f12c7c014303451399fc368d9112b24a |
| institution | Kabale University |
| issn | 1687-6075 1687-6083 |
| language | English |
| publishDate | 2011-01-01 |
| publisher | Wiley |
| record_format | Article |
| series | Science and Technology of Nuclear Installations |
| spelling | doaj-art-f12c7c014303451399fc368d9112b24a2025-02-03T07:26:03ZengWileyScience and Technology of Nuclear Installations1687-60751687-60832011-01-01201110.1155/2011/785304785304A Coupled Calculation Suite for Atucha II Operational Transients AnalysisOscar Mazzantini0Miguel Schivo1Julián Di Césare2Ricardo Garbero3Matías Rivero4Germán Theler5Grupo de Licencamiento, Seguridad y Cálculo del Núcleo, Unidad de Gestión Atucha II, Nucleoeléctrica Argentina S.A., 2806 Lima, ArgentinaGrupo de Licencamiento, Seguridad y Cálculo del Núcleo, Unidad de Gestión Atucha II, Nucleoeléctrica Argentina S.A., 2806 Lima, ArgentinaGrupo de Licencamiento, Seguridad y Cálculo del Núcleo, Unidad de Gestión Atucha II, Nucleoeléctrica Argentina S.A., 2806 Lima, ArgentinaGrupo de Licencamiento, Seguridad y Cálculo del Núcleo, Unidad de Gestión Atucha II, Nucleoeléctrica Argentina S.A., 2806 Lima, ArgentinaGrupo de Cálculo y Análisis de Sistemas Nucleares, TECNA Estudios y Proyectos de Ingeniería, C1107CLA Buenos Aires, ArgentinaGrupo de Cálculo y Análisis de Sistemas Nucleares, TECNA Estudios y Proyectos de Ingeniería, C1107CLA Buenos Aires, ArgentinaWhile more than a decade ago reactor and thermal hydraulic calculations were tedious and often needed a lot of approximations and simplifications that forced the designers to take a very conservative approach, computational resources available nowadays allow engineers to cope with increasingly complex problems in a reasonable time. The use of best-estimate calculations provides tools to justify convenient engineering margins, reduces costs, and maximises economic benefits. In this direction, a suite of coupled best-estimate specific calculation codes was developed to analyse the behaviour of the Atucha II nuclear power plant in Argentina. The developed tool includes three-dimensional spatial neutron kinetics, a channel-level model of the core thermal hydraulics with subcooled boiling correlations, a one-dimensional model of the primary and secondary circuits including pumps, steam generators, heat exchangers, and the turbine with all their associated control loops, and a complete simulation of the reactor control, limitation, and protection system working in closed-loop conditions as a faithful representation of the real power plant. In the present paper, a description of the coupling scheme between the codes involved is given, and some examples of their application to Atucha II are shown.http://dx.doi.org/10.1155/2011/785304 |
| spellingShingle | Oscar Mazzantini Miguel Schivo Julián Di Césare Ricardo Garbero Matías Rivero Germán Theler A Coupled Calculation Suite for Atucha II Operational Transients Analysis Science and Technology of Nuclear Installations |
| title | A Coupled Calculation Suite for Atucha II Operational Transients Analysis |
| title_full | A Coupled Calculation Suite for Atucha II Operational Transients Analysis |
| title_fullStr | A Coupled Calculation Suite for Atucha II Operational Transients Analysis |
| title_full_unstemmed | A Coupled Calculation Suite for Atucha II Operational Transients Analysis |
| title_short | A Coupled Calculation Suite for Atucha II Operational Transients Analysis |
| title_sort | coupled calculation suite for atucha ii operational transients analysis |
| url | http://dx.doi.org/10.1155/2011/785304 |
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