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Master's Dissertation
DOI
https://doi.org/10.11606/D.85.2023.tde-12042023-120926
Document
Author
Full name
Lucas Stano Junqueira
E-mail
Institute/School/College
Knowledge Area
Date of Defense
Published
São Paulo, 2023
Supervisor
Committee
Silva, Paulo Sergio Cardoso da (President)
Menezes, Maria Angela de Barros Correia
Ribeiro, Fernando Carlos Araujo
Title in Portuguese
Determinação da atividade de emissores beta e gama em rejeitos radioativos operacionais da central nuclear de Angra
Keywords in Portuguese
cromatografia de troca iônica
radionuclídeos de difícil medição
rejeito radioativo
separação radioquímica
Abstract in Portuguese
Todo rejeito radioativo precisa ser caracterizado para que seu repositório final seja definido conforme os critérios de segurança apresentados nas normas CNEN 6.06 e CNEN 6.09. Neste trabalho foram adaptadas metodologias para analisar os rejeitos radioativos de concentrado de evaporador e resinas de troca iônica das usinas nucleares de Angra dos Reis e determinar a concentração de atividade dos seguintes radionuclídeos de difícil medição: 63Ni, 59Ni, 90Sr, 129I e 135Cs, que apresentaram rendimento de separação, em média de 93, 40, 97 e 73% respectivamente. O 63Ni e o 59Ni foram separados por cromatografia de troca iônica em coluna de Ni resin da Eichron Technologies, o 63Ni foi medido por cintilação líquida e o 59Ni por espectrometria gama. O 90Sr foi separado por cromatografia de troca iônica em coluna Sr-spec e precipitação com oxalato. O 135Cs foi separado por cromatografia de troca iônica em coluna com resina Dowex 50W-X12 e coprecipitação com molibdato de amônio e o 129I foi separado por precipitação com PdCl2. As concentrações de atividade em Bq/g encontradas para o 59Ni ficaram entre 123 e 1685, para o 63Ni entre 40 e 6,53X105, para o 129I entre 0,61 e 535, para o 90Sr entre 0,35 e 58,04 e o 135Cs teve todas as suas medidas abaixo dos limites de detecção que variaram de 2,7 a 349. A metodologia desenvolvida para a separação do iodo não foi encontrada na literatura e apresenta melhorias significativas quando comparada com os métodos atuais para a mesma determinação.
Title in English
Activity determination of beta and gamma emitters in operational radioactive waste from Angra nuclear center
Keywords in English
hard to measure radionuclides
ionic exchange chromatography
radioactive waste
radiochemistry separation
Abstract in English
All the radioactive waste need to be characterized so that its final repository can be defined according to the safety criteria presented on the safety norms CNEN 6.06 and CNEN 6.09. In this study methodologies were developed to analyze nuclear waste from the nuclear power plants at Angra dos Reis and to determine the activity concentration of the following hard to measured nuclides: 63Ni, 59Ni, 90Sr, 129I e 135Cs, which presented separations yields, on average of 93, 40, 97 e 73% respectively. 63Ni and 59Ni were separated by ionic exchange chromatography in column with eichron ni-resin, 63Ni was measured by liquid scintillation and 59Ni was measured by gamma spectrometry. 90Sr was separated by ionic exchange chromatography with eichron Sr-spec and oxalate precipitation. 135Cs was separated by ionic exchange chromatography with Dowex 50W-X12 resin and coprecipitation with amonium molibdate. And 129I was separated by precipitation with PdCl2. The activity concentrations measured in Bq/g for 59Ni were between 123 and 1685, for 63Ni between 40 and 6.53X105, for 129I between 0.61 and 535, for 90Sr between 0.35 and 58.04 and 135Cs had all its measurements below the detection limit that varied from 2,7 to 349. The methodology presented for iodine separation was not found on the literature, and present significative enhancement when compered to current methods.
 
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Publishing Date
2023-04-14
 
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