Definition of parameters for a test section for the analysis of natural convection and coolant loss in the AP1000 nuclear reactor by similarity laws and fractional scaling analysis
The present work develops and analysis the main parameters of a test section for natural convection in case of failure of the pumping system as much as the loss of coolant in refrigeration accidents. For this realization a combination of laws of basic similarity and an innovative scale methodology,...
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| Format: | Article |
| Language: | English |
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Brazilian Radiation Protection Society (Sociedade Brasileira de Proteção Radiológica, SBPR)
2019-06-01
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| Series: | Brazilian Journal of Radiation Sciences |
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| Online Access: | https://bjrs.org.br/revista/index.php/REVISTA/article/view/616 |
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| author | Luis Felipe Serra Cadiz Mario Silva Fernando Roberto de Andrade Lima Carlos Alberto Oliveira |
| author_facet | Luis Felipe Serra Cadiz Mario Silva Fernando Roberto de Andrade Lima Carlos Alberto Oliveira |
| author_sort | Luis Felipe Serra Cadiz |
| collection | DOAJ |
| description | The present work develops and analysis the main parameters of a test section for natural convection in case of failure of the pumping system as much as the loss of coolant in refrigeration accidents. For this realization a combination of laws of basic similarity and an innovative scale methodology, known as Fractional Scaling Analysis (FSA), was de-veloped. The depressurizing is analyzed when a rupture occurs in one of the primary system piping of the AP1000 nuclear reactor. This reactor is developed by Westinghouse Electric Co., which is a PWR (Pressurized Water Reactor) with an electric power equal to 1000MW. Such a reactor is provided with a passive safety system that promotes con-siderable improvements in the safety, reliability, protection and reduction of costs of a nuclear power plant. The FSA is based on two concepts: fractional scale and hierarchy. It is used to provide experimental data that generate quantita-tive evaluation criteria as well as operational parameters in thermal and hydraulic processes of nuclear power plants. The results were analyzed with the use of computational codes. |
| format | Article |
| id | doaj-art-eaf3e06811eb45f49dedfce273023b94 |
| institution | Kabale University |
| issn | 2319-0612 |
| language | English |
| publishDate | 2019-06-01 |
| publisher | Brazilian Radiation Protection Society (Sociedade Brasileira de Proteção Radiológica, SBPR) |
| record_format | Article |
| series | Brazilian Journal of Radiation Sciences |
| spelling | doaj-art-eaf3e06811eb45f49dedfce273023b942025-08-20T03:51:04ZengBrazilian Radiation Protection Society (Sociedade Brasileira de Proteção Radiológica, SBPR)Brazilian Journal of Radiation Sciences2319-06122019-06-0172B (Suppl.)10.15392/bjrs.v7i2B.616471Definition of parameters for a test section for the analysis of natural convection and coolant loss in the AP1000 nuclear reactor by similarity laws and fractional scaling analysisLuis Felipe Serra Cadiz0Mario SilvaFernando Roberto de Andrade LimaCarlos Alberto OliveiraUFPEThe present work develops and analysis the main parameters of a test section for natural convection in case of failure of the pumping system as much as the loss of coolant in refrigeration accidents. For this realization a combination of laws of basic similarity and an innovative scale methodology, known as Fractional Scaling Analysis (FSA), was de-veloped. The depressurizing is analyzed when a rupture occurs in one of the primary system piping of the AP1000 nuclear reactor. This reactor is developed by Westinghouse Electric Co., which is a PWR (Pressurized Water Reactor) with an electric power equal to 1000MW. Such a reactor is provided with a passive safety system that promotes con-siderable improvements in the safety, reliability, protection and reduction of costs of a nuclear power plant. The FSA is based on two concepts: fractional scale and hierarchy. It is used to provide experimental data that generate quantita-tive evaluation criteria as well as operational parameters in thermal and hydraulic processes of nuclear power plants. The results were analyzed with the use of computational codes.https://bjrs.org.br/revista/index.php/REVISTA/article/view/616ap1000locafsa |
| spellingShingle | Luis Felipe Serra Cadiz Mario Silva Fernando Roberto de Andrade Lima Carlos Alberto Oliveira Definition of parameters for a test section for the analysis of natural convection and coolant loss in the AP1000 nuclear reactor by similarity laws and fractional scaling analysis Brazilian Journal of Radiation Sciences ap1000 loca fsa |
| title | Definition of parameters for a test section for the analysis of natural convection and coolant loss in the AP1000 nuclear reactor by similarity laws and fractional scaling analysis |
| title_full | Definition of parameters for a test section for the analysis of natural convection and coolant loss in the AP1000 nuclear reactor by similarity laws and fractional scaling analysis |
| title_fullStr | Definition of parameters for a test section for the analysis of natural convection and coolant loss in the AP1000 nuclear reactor by similarity laws and fractional scaling analysis |
| title_full_unstemmed | Definition of parameters for a test section for the analysis of natural convection and coolant loss in the AP1000 nuclear reactor by similarity laws and fractional scaling analysis |
| title_short | Definition of parameters for a test section for the analysis of natural convection and coolant loss in the AP1000 nuclear reactor by similarity laws and fractional scaling analysis |
| title_sort | definition of parameters for a test section for the analysis of natural convection and coolant loss in the ap1000 nuclear reactor by similarity laws and fractional scaling analysis |
| topic | ap1000 loca fsa |
| url | https://bjrs.org.br/revista/index.php/REVISTA/article/view/616 |
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