Characterization of ceramics supports of titanium oxide for treatment of the radioactive liquid waste nuclear
Palavras-chave:
ceramic membranes, titanium oxide, treatment of the nuclear wasteResumo
Structural charcteristics ceramics supports of titanium oxide for treatment of the radioactive liquid nuclear waste were analysed. Supports were sintered in tempertaures of 1100 ºC and 1150ºC. Different quantities of starch (0, 15 and 30%) were added to ensure later pore formation during sintering. The hydraulic permeability was calculated from the permeate flow with water (L m-2 h-1) at pressures of 1 to 4 bar. The porosity suggested for application as support is around 40%, being obtained in this study porosity of 42% with 0 and 15% of starch in both sintering temperatures. The permeability was determined for the condition 15% of starch at 1100 and 1150ºC, presenting values of 95 and 82 Lm-2 h-1 bar-1, respectively. In the case of pure solvents and considering that it does not react with the support, the permeate flow will have a linear dependence with the pressure and the angular coefficient of the line will be the hydraulic permeability. These values correspond to the permeability of microfiltration membranes.Referências
BORGES, C. P.; HABERT, A. C.; NOBREGA, R. Processos de separação por membranas. Rio de Janeiro: E-papers, 2006. 180p.
SANTOS J. G.; CORREA R. A.; OGASAWARA, T. Synthesis of mesoporous titania in rutile phase with pore-stable Structure. Brazilian Journal of Chemical Engineering, São Paulo, v. 26, n. 3, p. 555-561, set. 2009.
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2021-07-08
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Develop. and charact. of Functional and Structural Materials in Nuclear Industry
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Copyright (c) 2018 Elizabeth Eugenio de Mello Oliveira, Milena Hudson Silva
Este trabalho está licenciado sob uma licença Creative Commons Attribution-NonCommercial-NoDerivatives 4.0 International License.