Please use this identifier to cite or link to this item:
http://www.repositorio.cdtn.br:8080/jspui/handle/123456789/1034| Title: | Experimental determination of heat transfer coeficients in uranium zirconium hydride fuel rod |
| metadata.dc.title.evento: | INAC International Nuclear Atlantic Conference, ENFIR Meeting on Reactor Physics and Thermal Hydraulics, 14 |
| Authors: | Mesquita, Amir Zacarias Rezende, Hugo Cesar Costa, Antônio Carlos L. da |
| Affiliation: | Centro de Desenvolvimento da Tecnologia Nuclear/CDTN, Belo Horizonte, MG, Brasil Centro de Desenvolvimento da Tecnologia Nuclear/CDTN, Belo Horizonte, MG, Brasil Centro de Desenvolvimento da Tecnologia Nuclear/CDTN, Belo Horizonte, MG, Brasil |
| Issue Date: | 2005 |
| Keywords: | TRIGA-Brazil reactor;heat transfer;fuel rods;uranium hydrides;zirconium hydrides |
| Abstract: | This work presents the experiments and theoretical analysis to determine the temperature parameter of the uranium zirconium hydride fuel elements, used in the TRIGA IPR-R1 research nuclear reactor. |
| Access: | L |
| Appears in Collections: | Trabalho apresentado em evento |
Files in This Item:
| File | Description | Size | Format | |
|---|---|---|---|---|
| Art-01_AmirZ_Mesquita.pdf | 150.31 kB | Adobe PDF | View/Open |
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