Temperature and heat flux calculations for the maximum power channel of the TRIGA IAN-R1 research reactor
With cooperation of the International Atomic Energy Agency (IAEA), thermal-hydraulic calculations were carried out for conversion of the IAN-R1 Reactor from MTR-HEU fuel to TRIGA-LEU fuel. To establish thermal-hydraulic calculation and analysis research in Colombia, this program was carried out and...
| Main Authors: | , |
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| Format: | Article |
| Language: | Spanish |
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Servicio Geológico Colombiano
2019-12-01
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| Series: | Revista Investigaciones y Aplicaciones Nucleares |
| Subjects: | |
| Online Access: | https://revistas.sgc.gov.co/index.php/invapnuclear/article/view/509 |
| _version_ | 1797954330738819072 |
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| author | José Antonio Sarta Luis Álvaro Castiblanco |
| author_facet | José Antonio Sarta Luis Álvaro Castiblanco |
| author_sort | José Antonio Sarta |
| collection | DOAJ |
| description |
With cooperation of the International Atomic Energy Agency (IAEA), thermal-hydraulic calculations were carried out for conversion of the IAN-R1 Reactor from MTR-HEU fuel to TRIGA-LEU fuel. To establish thermal-hydraulic calculation and analysis research in Colombia, this program was carried out and included training, acquisition of hardware, software and natural convection flow calculations for the TRIGA IAN-R1 research reactor operating at 100 kW. The purpose of the study is to validate the steady state thermal hydraulic analysis that has been carried out by means of the NATCON code. This paper presents the results of the maximum axial temperature distribution for fuel, clad, and coolant. In addition, the Bernath critical heat flux with pool water temperature as a parameter is presented.
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| first_indexed | 2024-04-10T23:15:56Z |
| format | Article |
| id | doaj.art-d5bf42feaa9d45f598589216eaf46ebe |
| institution | Directory Open Access Journal |
| issn | 2590-7468 2711-1326 |
| language | Spanish |
| last_indexed | 2024-04-10T23:15:56Z |
| publishDate | 2019-12-01 |
| publisher | Servicio Geológico Colombiano |
| record_format | Article |
| series | Revista Investigaciones y Aplicaciones Nucleares |
| spelling | doaj.art-d5bf42feaa9d45f598589216eaf46ebe2023-01-12T19:33:47ZspaServicio Geológico ColombianoRevista Investigaciones y Aplicaciones Nucleares2590-74682711-13262019-12-01310.32685/2590-7468/invapnuclear.3.2019.509317Temperature and heat flux calculations for the maximum power channel of the TRIGA IAN-R1 research reactorJosé Antonio SartaLuis Álvaro Castiblanco With cooperation of the International Atomic Energy Agency (IAEA), thermal-hydraulic calculations were carried out for conversion of the IAN-R1 Reactor from MTR-HEU fuel to TRIGA-LEU fuel. To establish thermal-hydraulic calculation and analysis research in Colombia, this program was carried out and included training, acquisition of hardware, software and natural convection flow calculations for the TRIGA IAN-R1 research reactor operating at 100 kW. The purpose of the study is to validate the steady state thermal hydraulic analysis that has been carried out by means of the NATCON code. This paper presents the results of the maximum axial temperature distribution for fuel, clad, and coolant. In addition, the Bernath critical heat flux with pool water temperature as a parameter is presented. https://revistas.sgc.gov.co/index.php/invapnuclear/article/view/509temperatureheat fluxdeparture from nucleate boiling |
| spellingShingle | José Antonio Sarta Luis Álvaro Castiblanco Temperature and heat flux calculations for the maximum power channel of the TRIGA IAN-R1 research reactor Revista Investigaciones y Aplicaciones Nucleares temperature heat flux departure from nucleate boiling |
| title | Temperature and heat flux calculations for the maximum power channel of the TRIGA IAN-R1 research reactor |
| title_full | Temperature and heat flux calculations for the maximum power channel of the TRIGA IAN-R1 research reactor |
| title_fullStr | Temperature and heat flux calculations for the maximum power channel of the TRIGA IAN-R1 research reactor |
| title_full_unstemmed | Temperature and heat flux calculations for the maximum power channel of the TRIGA IAN-R1 research reactor |
| title_short | Temperature and heat flux calculations for the maximum power channel of the TRIGA IAN-R1 research reactor |
| title_sort | temperature and heat flux calculations for the maximum power channel of the triga ian r1 research reactor |
| topic | temperature heat flux departure from nucleate boiling |
| url | https://revistas.sgc.gov.co/index.php/invapnuclear/article/view/509 |
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