Please use this identifier to cite or link to this item:
http://www.repositorio.cdtn.br:8080/jspui/handle/123456789/1083| metadata.dc.title.evento: | ENC European nuclear confrence |
| Affiliation: | Centro de Desenvolvimento da Tecnologia Nuclear/CDTN, Belo Horizonte, MG, Brasil Centro de Desenvolvimento da Tecnologia Nuclear/CDTN, Belo Horizonte, MG, Brasil |
| Issue Date: | 2010 |
| Keywords: | Triga-Brazil reactor;safety;neutron flux;termal hydraulics |
| Abstract: | The IPR-R1 TRIGA reactor, located at CDTN (Belo Horizonte/Brazil), is a typical 100 kW Mark I light-water reactor cooled by assisted natural convection with an annular graphite reflector. In order to study the safety aspects connected with the increase of the maximum steady state power of the IPR-R1 TRIGA reactor, experimental measures were taken. This paper summarizes the experimental program and some recent results and procedures of the neutronic and thermalhydraulic experiments carried out in the IPR-R1 TRIGA reactor. |
| Access: | L |
| Appears in Collections: | Trabalho apresentado em evento |
Files in This Item:
| File | Description | Size | Format | |
|---|---|---|---|---|
| Art-33_Amir_ZMesquita.pdf | 421.69 kB | Adobe PDF | View/Open |
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