Chemical treatment of simulated solution of evaporator concentrate for immobilization in bitumen

Awwal, M.A.; Guzella, Marcia F. R.; Silva, T.V.

doi:10.1016/s0956-053x(96)00018-9

Cited by 7 publications

(2 citation statements)

References 5 publications

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“…Têm sido realizadas pesquisas visando à utilização de betumes nacionais como matriz para incorporação de rejeitos de usinas nucleares (AWWAL et al, 1994;GUZELLA et al, 1999GUZELLA et al, , 2001bGUZELLA et al, , 2005. A utilização de materiais nacionais visa tornar o país independente de importação, reduzir custos e incentivar pesquisas na área, na tentativa de melhoria contínua do processo.…”

Section: Pand D Em Tratamento De Rejeitos Apoio a Usinas Nuclearesunclassified

“…A partir das campanhas de incorporação e da avaliação dos resultados pôde se constatar que a variável de processo com efeito significativo para as variáveis resposta, taxas de lixiviação de boro e sódio em um ano foi o tipo de Este composto é obtido após tratamento da solução de concentrado de evaporador em condições controláveis. O pré tratamento para a obtenção da ulexita, anterior à incorporação do rejeito em uma matriz de betume é sugerido em literatura (AWWAL et al, 1996), como uma forma de reduzir o inchamento dos produtos de rejeito, quando em processo de lixiviação. Na obtenção da ulexita, há a formação de borato de sódio e cálcio provenientes do ácido bórico presente na solução de rejeito.…”

Section: Borounclassified

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Desenvolvimento de processo para imobilização de rejeitos de usinas nucleares utilizando betumes nacionais

Guzella¹,

Jordão²

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The main goal of this work is the development of a process to incorporate radioactive wastes from nuclear power plants into bitumen matrice. This process aims at obtaining waste forms that are monolithic, homogeneous and mechanical and chemically stable with low leaching rates. These features are important to evaluate the waste forms according to national and international standards. The obtained waste forms should meet the standard safety criteria for disposal in order to be accepted in a repository. Two Brazilian bitumens with softening point of 71,8 o C and 91,3 o C, respectively, were evaluated. The evaporator concentrate waste was selected to be used due to the large volume of this kind of waste generated in a PWR nuclear power plant. The two bitumens were evaluated so that the Brazilian material could be used to incorporate radioactive wastes thus avoiding the import of foreign raw material specified to other nuclear power plants in Europe, for instance. The immobilization campaigns were performed at the Bituminization Pilot Plant at CDTN and the incorporated waste concentrations ranged from 30 wt% to 40 wt%, which are in accordance with data from literature and also from plants that use the bituminization process. Important properties for bitumens and waste forms were evaluated in order to assure not only the system and occupational safety but also the quality of the waste forms which are developed to be stored for a long time in a repository. The analyzed properties are the penetration, the softening point, the flash point, the water content and the leaching rate. The integrity and durability of solid radioactive waste are also related to the waste constituents leaching rates in water. The procedure to determine such leaching rates are rule established and the analysis of these data is used to investigate the leaching mechanisms (diffusion, dissolution, partition) in order to determine the waste form performance and the experiment modeling. These analyses should be carried out before the waste form disposal and are important for safety assessment purposes. This research has also contributed not only to the development of the bituminization process to incorporate waste but also to the improvement of the Bituminization Pilot Plant at CDTN and to the implementation of methodologies and techniques to characterize bitumens and waste forms. This work concludes that is feasible to use the evaluated Brazilian bitumens for immobilization of nuclear power plants wastes in Brazil, obtaining waste forms with the required properties to be disposal in repository.

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Section: Pand D Em Tratamento De Rejeitos Apoio a Usinas Nuclearesunclassified

Section: Borounclassified

Desenvolvimento de processo para imobilização de rejeitos de usinas nucleares utilizando betumes nacionais

Guzella¹,

Jordão²

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Comparison of radioactive transmission and mechanical properties of Portland cement and a modified cement with trommel sieve waste

Boncukçuoğlu

İçelli

Erzeneoğlu

et al. 2005

Cement and Concrete Research

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Rapid immobilization of simulated radionuclide Nd at low temperatures by flash reaction

Lian

Ren

Wang

et al. 2019

Ceramics International

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Chemical treatment of simulated solution of evaporator concentrate for immobilization in bitumen

Cited by 7 publications

References 5 publications

Desenvolvimento de processo para imobilização de rejeitos de usinas nucleares utilizando betumes nacionais

Desenvolvimento de processo para imobilização de rejeitos de usinas nucleares utilizando betumes nacionais

Comparison of radioactive transmission and mechanical properties of Portland cement and a modified cement with trommel sieve waste

Rapid immobilization of simulated radionuclide Nd at low temperatures by flash reaction

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