Cinética de sinterização do combustível nuclear 'UO IND. 2.'7%'Gd IND.2''O IND. 3': cálculo da curva mestre de sinterização
Carregando...
Arquivos
Data
2010-03-05
Autores
Silva, Selma Luiza [UNESP]
Título da Revista
ISSN da Revista
Título de Volume
Editor
Universidade Estadual Paulista (Unesp)
Resumo
O processo de sinterização de pastilhas de 'UO IND. 2.'7%'Gd IND.2''O IND. 3' tem sido investigado por muito tempo devido à sua importância na indústria nuclear e ao seu comportamento complexo durante o adensamento. Vários pesquisadores tentaram explicar este comportamento utilizando uma abordagem fenomenológica. Ainda que com algum sucesso, o comportamento na sinterização é difícil de ser previsto. A densidade final e a microestrutura da pastilha sinterizada dependem das propriedades dos pós de partida, do perfil térmico, da composição da atmosfera, da presença de aditivos, entre outras variáveis. Uma abordagem diferente do problema supera esta dificuldade com a introdução do conceito da Curva Mestre de Sinterização - CMS. A CMS do combustível nuclear 'UO IND. 2.'7%'Gd IND.2''O IND. 3' foi levantada utilizando dados de dilatometria obtidos com a taxa de aquecimento constante. Este desenvolvimento foi realizado para prever e controlar a evolução da densidade durante a etapa de sinterização. As amostras foram produzidas através da mistura do pós de 'UO IND. 2' e 'Gd IN> 2''O IND. 3', compactadas e sinterizadas em um dilatômetro a 2023 k, com diferentes taxas de aquecimento na faixa de 5 a 45 'Kmin. POT. -1', sob atmosfera de 'H IND. 2'. Com base no conceito da CMS, a previsão do adensamento foi realizada e uma boa concordância entre os valores previstos e experimental foi verificada. Foi demonstrado que o conceito da CMS pode ser utilizado para planejar um perfil de temperatura adequado, visando uma densidade final desejada, mesmo para sistemas com reações mais complexas como o 'UO IND. 2.'7%'Gd IND.2''O IND. 3'. A energia de ativação aparente do processo de sinterização pode ser estimada por este método.
The sintering process of the 'UO IND. 2.'7%'Gd IND.2''O IND. 3' system has been investigated for a long time due to its economical importance to the nuclear industry and complex behavior during densification. Most researchers tried to describe and explain it using a phenomenological approach. Even though some light has been shed on the matter, the system sintering behavior is still very difficult to predict. The final density and microstructure of the sintered body is strongly dependent on properties of raw powders, temperature profile,, atmosphere composition, presence of sintering additives, among other process variables. A different approach to the problem overcame this difficulty by introducing the concept of the Master Sintering Curve - MSC. The MSC of the 'UO IND. 2.'7%'Gd IND.2''O IND. 3' nuclear fuel was constructed using constant heating rate dilatometry data. This development was carried out to predict and control the evolution of the density during the sintering path. The samples were produced from a dry misture of UO IND. 2' and 2' e 'Gd IN> 2''O IND. 3' powders, pressed into compacts and sintered in a dilatometer up to 2023 K with different heating rates from 5 to 45 'Kmin. POT. -1', under a 'H IND. 2' atmosphere. Based on the MSC concept, the prediction of pellet densification was performed and it was observed a good agreement between the experimental and the predicted values. It was demonstrated that the MSC approach can be used to desing a suitable sintering temperature profile in order to obtain a desidered final density, even for reacting systems such as the 'UO IND. 2.'7%'Gd IND.2''O IND. 3', where the second phase should mostley get into solution. The apparent activation energy of sintering process could also be estimated by this method.
The sintering process of the 'UO IND. 2.'7%'Gd IND.2''O IND. 3' system has been investigated for a long time due to its economical importance to the nuclear industry and complex behavior during densification. Most researchers tried to describe and explain it using a phenomenological approach. Even though some light has been shed on the matter, the system sintering behavior is still very difficult to predict. The final density and microstructure of the sintered body is strongly dependent on properties of raw powders, temperature profile,, atmosphere composition, presence of sintering additives, among other process variables. A different approach to the problem overcame this difficulty by introducing the concept of the Master Sintering Curve - MSC. The MSC of the 'UO IND. 2.'7%'Gd IND.2''O IND. 3' nuclear fuel was constructed using constant heating rate dilatometry data. This development was carried out to predict and control the evolution of the density during the sintering path. The samples were produced from a dry misture of UO IND. 2' and 2' e 'Gd IN> 2''O IND. 3' powders, pressed into compacts and sintered in a dilatometer up to 2023 K with different heating rates from 5 to 45 'Kmin. POT. -1', under a 'H IND. 2' atmosphere. Based on the MSC concept, the prediction of pellet densification was performed and it was observed a good agreement between the experimental and the predicted values. It was demonstrated that the MSC approach can be used to desing a suitable sintering temperature profile in order to obtain a desidered final density, even for reacting systems such as the 'UO IND. 2.'7%'Gd IND.2''O IND. 3', where the second phase should mostley get into solution. The apparent activation energy of sintering process could also be estimated by this method.
Descrição
Palavras-chave
Sinterização, Curva mestre de sinterização, Combustível nuclear, Sintering process, Phenomenological approach, Master Sintering Curve
Como citar
SILVA, Selma Luiza. Cinética de sinterização do combustível nuclear 'UO IND. 2.'7%'Gd IND.2''O IND. 3': cálculo da curva mestre de sinterização. 2010. 135 f. Dissertação (mestrado) - Universidade Estadual Paulista, Faculdade de Ciências, 2010.