Abstract: Neste trabalho, a influência de diferentes materiais do eletrodo coletor na resposta de uma câmara de ionização de extrapolação foi avaliada. Esta câmara de ionização foi simulada com o código de Monte Carlo MCNP-4C e foi utilizado o espectro de um feixe padrão de radiodiagnóstico (RQR5). Os diferentes resultados obtidos se devem às interações dos fótons com diferentes materiais do eletrodo coletor, contribuírem com valores diferentes de energias depositadas no volume sensível da câmara de ionização, as quais dependem do número atômico dos materiais avaliados. O material que apresentou menor influência foi o grafite, constituinte original da câmara de ionização.

Palavras-Chave: aluminium; beta dosimetry; computerized tomography; electrodes; extrapolation chambers; graphite; iron; materials; monte carlo method; silver

VEDOVATO, ULY P.; NEVES, LUCIO P.; SANTOS, WILLIAM S.; BELINATO, WALMIR; CALDAS, LINDA V.E.; PERINI, ANA P. Estudo do material do eletrodo coletor de uma câmara de extrapolação por simulação de Monte Carlo. In: CONGRESSO BRASILEIRO DE METROLOGIA, 9.; CONGRESSO INTERNACIONAL DE METROLOGIA MECANICA, 4.; CONGRESSO INTERNACIONAL DE METROLOGIA ELETRICA, 12.; CONGRESSO BRASILEIRO DE METROLOGIA DAS RADIAÇOES IONIZANTES, 4.; WORKSHOP DA REDE DE METROLOGIA QUIMICA DO INMETRO, 3.; CONGRESSO BRASILEIRO DE METROLOGIA OPTICA, 2., 26-29 de novembro, 2017, Fortaleza, CE. Anais... Rio de Janeiro, RJ: Sociedade Brasileira de Metrologia, 2017. p. 1-4. Disponível em: http://repositorio.ipen.br/handle/123456789/28594. Acesso em: $DATA.

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Abstract: Este trabalho evidencia o processamento químico do urânio natural desde a fase “yellowcake” até a produção de hexafluoreto de urânio UF6 natural, processo este realizado na usina piloto do IPEN-CNEN/SP .O gerenciamento de radioproteção tinha por atividades monitorar os indivíduos ocupacionalmente expostos IOEs, o local de trabalho e meio ambiente. Por esta razão desenvolveu-se um programa de monitoração individual para o IOE tanto para irradiações externas quanto para incorporação do material radioativo. Os IOEs eram monitorados externamente com dosímetros tipo filme e internamente aplicou-se o método in vitro para análise de urina. Para o local de trabalho desenvolveu-se o programa de monitoração para equipamentos e pisos determinando a taxa de exposição proveniente dos equipamentos de processo, contaminação superficial expressa em Bq.cm-2 em equipamentos e pisos, complementando com o programa de monitoração do ar tanto para o trabalhador como para o local de trabalho .Utilizou-se filtros de celulose com diâmetro aerodinâmico de 0,3 micra até 8,0 micra.

SILVA, TERESINHA de M. da; SORDI, GIAN M.A.A.; VASQUES, FRANCISCO M.F. Programa de radioproteção aplicado aos indivíduos ocupacionalmente expostos na usina piloto do IPEN-CNEN/SP na década de 80 para compostos de urânio natural. In: INTERNATIONAL JOINT CONFERENCE RADIO 2017, September 24-29, 2017, Goiânia, GO. Proceedings... Maringá, PR: Sociedade Brasileira de Proteção Radiológica, 2017. p. 1-5. Disponível em: http://repositorio.ipen.br/handle/123456789/28592. Acesso em: $DATA.

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Abstract: Este estudo tem por objetivo abordar alguns requisitos básicos de controle de exposição dos IOE durante a fase de pro-jeto de instalações nucleares de apoio terrestre a embarcações marítimas. Para tanto, foram utilizados guias regulatórios americanos, normas da CNEN e experiências adquiridas em instalações nucleares convencionais. O projeto da instala-ção deverá considerar a provisão de dispositivos móveis para o atendimento às monitorações e descontaminações. Por fim, observa-se que o estabelecimento de critérios adicionais de controle de exposição pode impactar diretamente nos projetos civil, arquitetônico e eletromecânico da instalação, desde a fase conceitual.

LARA, E.G.; PINHEIRO, A.R.M.; BARONI, D.B.; SANTOS, F.C.; BORSOI, S.S.; SILVA, T.P. Controle de exposição dos indivíduos em instalações nucleares de apoio terrestre a embarcações marítimas. In: INTERNATIONAL JOINT CONFERENCE RADIO 2017, September 24-29, 2017, Goiânia, GO. Proceedings... Maringá, PR: Sociedade Brasileira de Proteção Radiológica, 2017. p. 1-3. Disponível em: http://repositorio.ipen.br/handle/123456789/28590. Acesso em: $DATA.

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Abstract: O estudo discute as situações no ambiente industrial que podem levar à exposição potencial de Indivíduos Ocupacionalmente Expostos e Indivíduos do Público em aceleradores de elétrons autoblindados. Embora estas situações de exposição sejam pouco prováveis, exercícios de simulação podem levar à melhorias no procedimento de operação, bem como sugerir mudanças no projeto da linha de produção a fim de aumentar a proteção radiológica no trabalho. Estes estudos também podem ser usados em treinamentos e demonstram uma aplicação sólida do princípio ALARA nas atividades diárias das instalações radiativas.

RIOS, D.A.S.; RIOS, P.B.; SORDI, G.M.A.A.; CARNEIRO, J.C.G.G. Situações de exposição potencial em aceleradores de elétrons autoblindados. In: INTERNATIONAL JOINT CONFERENCE RADIO 2017, September 24-29, 2017, Goiânia, GO. Proceedings... Maringá, PR: Sociedade Brasileira de Proteção Radiológica, 2017. p. 1-4. Disponível em: http://repositorio.ipen.br/handle/123456789/28588. Acesso em: $DATA.

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Abstract: Neste trabalho é avaliada a uniformidade de fontes extensas de referência circular, que ainda são bastante utilizadas no Brasil. Em trabalhos anteriores foram analisadas fontes extensas de referência retangular mostrando-se a importância da aplicação de fatores de correção na calibração de monitores de radiação. Agora é realizada uma transposição de métodos usados então, avaliando-se as uniformidades de fontes de referência circular e calculando-se os fatores de correção associados.

SILVA JUNIOR, I.A.; XAVIER, M.; SIQUEIRA, P.T.D.; SORDI, G.A.A.; POTIENS, M.P.A. Avaliação da uniformidade de fonte extensa de referência circular e aplicação de fatores de correção. In: CONGRESSO BRASILEIRO DE METROLOGIA, 9.; CONGRESSO INTERNACIONAL DE METROLOGIA MECANICA, 4.; CONGRESSO INTERNACIONAL DE METROLOGIA ELETRICA, 12.; CONGRESSO BRASILEIRO DE METROLOGIA DAS RADIAÇOES IONIZANTES, 4.; WORKSHOP DA REDE DE METROLOGIA QUIMICA DO INMETRO, 3.; CONGRESSO BRASILEIRO DE METROLOGIA OPTICA, 2., 26-29 de novembro, 2017, Fortaleza, CE. Anais... Rio de Janeiro, RJ: Sociedade Brasileira de Metrologia, 2017. p. 1-4. Disponível em: http://repositorio.ipen.br/handle/123456789/28586. Acesso em: $DATA.

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Abstract: Um sistema Tandem consiste na utilização de dosímetros com dependência energética diferentes, onde a razão entre as respostas das curvas de calibração em energia fornece a energia efetiva do feixe. A eficiência deste sistema está relacionada com as incertezas inerentes ao dosímetro utilizado e ao grau de dependência energética de cada conjunto. Quanto maior a inclinação da curva Tandem melhor será a identificação dos valores próximos de CSR tornando o sistema útil. Neste trabalho, o sistema Tandem é formado por câmara de ionização do tipo lápis e capas absorvedoras cilíndricas de materiais com diferentes dependências energéticas, para aplicação em tomografia computadorizada.

FONTES, LADYJANE P.; POTIENS, MARIA da P.A. Análise de curvas Tandem obtidas por meio de conjuntos de capas absorvedoras cilíndricas e câmara de ionização do tipo lápis para avaliação de CSR em Tomografia Computadorizada. In: CONGRESSO BRASILEIRO DE METROLOGIA, 9.; CONGRESSO INTERNACIONAL DE METROLOGIA MECANICA, 4.; CONGRESSO INTERNACIONAL DE METROLOGIA ELETRICA, 12.; CONGRESSO BRASILEIRO DE METROLOGIA DAS RADIAÇOES IONIZANTES, 4.; WORKSHOP DA REDE DE METROLOGIA QUIMICA DO INMETRO, 3.; CONGRESSO BRASILEIRO DE METROLOGIA OPTICA, 2., 26-29 de novembro, 2017, Fortaleza, CE. Anais... Rio de Janeiro, RJ: Sociedade Brasileira de Metrologia, 2017. p. 1-5. Disponível em: http://repositorio.ipen.br/handle/123456789/28584. Acesso em: $DATA.

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Abstract: Considered the largest urban radiological accident in the world, the accident in Goiânia with Cesium-137 resulted in the death of four people and injuries in another 49, besides measurable levels of internal or exter-nal contamination in 129. The accident generated also environmental contamination and thousands of tons of radioactive waste that resulted from the response activities. The accident occurred as a result of the disman-tling of an equipment of radiotherapy by employees of a junkyard. Before the accident was identified, con-taminated materials were sent to recycling companies in the state of São Paulo. The objective of this work was to report the existence of waste from Goiânia accident in the state of São Paulo and to check the estimat-ed activities at the time of the waste conditioning by measuring the current dose rates in waste packages, allowing a refinement of previously applied calculations.

SOUZA, D.C.B. de; GERALDO, B.; TESSARO, A.P.G.; ROSTELATO, M.E.C.M.; MARUMO, J.T.; CARVALHO, V.S.; BARBOSA, N.K.O.; VICENTE, R. Radioactive waste management Goiânia - São Paulo: 30 years later. In: INTERNATIONAL JOINT CONFERENCE RADIO 2017, September 24-29, 2017, Goiânia, GO. Proceedings... Maringá, PR: Sociedade Brasileira de Proteção Radiológica, 2017. p. 1-3. Disponível em: http://repositorio.ipen.br/handle/123456789/28582. Acesso em: $DATA.

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Abstract: Este estudo discute o risco ocupacional sob três aspectos distintos, que muitas vezes apresentam-se interligados ou são interdependentes no ambiente laboral. São eles: riscos ambientais, falhas humanas e falhas de equipamento. O artigo aborda a exposição potencial no ambiente de trabalho, causada pelo agente do risco físico radiação, resultante do manuseio com fontes de radiação ionizante. Baseado no histórico dos acidentes ocorridos em operações normais, o estudo apresenta um resumo dos principais acidentes em diversas instalações e possíveis causas envolvendo os três aspectos do risco. Em suas considerações finais, apresenta as lições aprendidas e as medidas a serem tomadas com o intuito de contribuir para a prevenção e mitigação dos riscos no ambiente laboral. A análise dos casos de acidentes e suas causas fornecem informações valiosas para a prevenção dos riscos de acidentes similares e contribuem para o aprimoramento dos projetos e procedimentos operacionais.

CARNEIRO, J. C. G.; LEVY, D.; SANCHES, M.P.; RODRIGUES, D.L.; SORDI, G.M.A.A. Percepção de risco no processo de trabalho com fontes de radiação. In: INTERNATIONAL JOINT CONFERENCE RADIO 2017, September 24-29, 2017, Goiânia, GO. Proceedings... Maringá, PR: Sociedade Brasileira de Proteção Radiológica, 2017. p. 1-5. Disponível em: http://repositorio.ipen.br/handle/123456789/28580. Acesso em: $DATA.

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Abstract: O principal objetivo deste estudo é relatar a experiência adquirida nas ações tomadas durante o processo de descontaminação de uma instalação do Instituto de Pesquisas Energéticas e Nucleares, IPEN-CNEN/SP, com o propósito de tornar o local para uso irrestrito. As etapas desta operação envolveram: planejamento, treinamento dos operadores da instalação, análise do local de trabalho e medidas radiométricas. A instalação continha diversos tipos de equipamentos oriundos da torre de produção de hexafluoreto de urânio natural, (UF6) e materiais de outras instalações. Foram estabelecidas regras para o transporte de materiais radioativos, no âmbito interno e externo da instalação e liberação de materiais e da instalação.

ALMEIDA, CLAUDIO C. de; SILVA, TERESINHA M.; RODRIGUES, DEMERVAL L.; CARNEIRO, JANETE C.G.G. Processo de descontaminação de superfícies em uma instalação de produção de hexafluoreto de urânio natural, (UF6). In: INTERNATIONAL JOINT CONFERENCE RADIO 2017, September 24-29, 2017, Goiânia, GO. Proceedings... Maringá, PR: Sociedade Brasileira de Proteção Radiológica, 2017. p. 1-5. Disponível em: http://repositorio.ipen.br/handle/123456789/28578. Acesso em: $DATA.

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Abstract: A utilização de lasers de pulsos ultracurtos é uma alternativa para a realização de microusinagem em superfícies de metais, com aplicações diversas em inúmeros segmentos industriais, além das áreas aeronáutica, aeroespacial e naval, onde há crescente preocupação com a eletrônica embarcada. Neste trabalho foram realizadas microusinagens em superfícies de titânio utilizando laser de pulsos ultracurtos de femtossegundos. Tal processo resultou em mínima transferência de calor para o material, evitando assim e deformação superficial da chapa de titânio e a formação de material ressolidificado na região ablacionada, que são inconvenientes presentes na utilização do laser chaveado de pulsos longos da ordem de nanossegundos. Foram executados três tipos de microusinagens, com variações nas distâncias entre as linhas usinadas. Foi verificado ainda que a molhabilidade aumenta quando há o aumento da distância entre linhas usinadas. Finalmente, para a alteração da superfície com uma ínfima remoção de material, constatou-se que a utilização de lasers de pulsos ultracurtos proporcionam grandes benefícios para a integridade do material ablacionado.

NOGUEIRA, ALESSANDRO F.; SAMAD, RICARDO E.; VIEIRA JUNIOR, NILSON D.; LIMA, MILTON S.F. de; ROSSI, WAGNER de. Estudo da ablação em superfícies de metais irradiadas com laser de femtossegundo. In: ABM WEEK; CONGRESSO ANUAL DA ABM, 72.; ENCONTRO NACIONAL DE ESTUDANTES DE ENGENHARIA METALURGICA, DE MATERIAIS E DE MINAS, 17., 02-06 de outubro, 2017, São Paulo, SP. Anais... São Paulo, SP: Associação Brasileira de Metalurgia, Materiais e Mineração, 2017. p. 1429-1440. Disponível em: http://repositorio.ipen.br/handle/123456789/28560. Acesso em: $DATA.

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Abstract: Lasers de pulsos ultracurtos têm sido utilizados como uma tecnologia de fabricação que tem possibilitado modificações nas superfícies de saída de ferramentas de corte por meio da texturização. Este tipo de laser é capaz de produzir uma ablação muito mais precisa do que os lasers convencionais, uma vez que a duração de seus pulsos é menor do que o período de vibração térmica da rede cristalina, o que minimiza a zona afetada pelo calor e preserva as propriedades do material. Neste contexto, o objetivo deste trabalho é avaliar o desempenho de ferramentas de corte de cerâmica branca texturizadas com lasers de pulsos ultracurtos. A superfície de saída das ferramentas foram texturizadas em dois padrões, variando o passo entre os canais. Ensaios de torneamento cilíndrico externo em ferro fundido cinzento foram executados com ferramentas texturizadas e não texturizadas (referência) para comparação de efeitos, mantendo as condições de corte constantes. Os esforços de corte, a rugosidade da peça e a integridade das ferramentas foram as variáveis de saída monitoradas. Os resultados mostraram que não houve diferença entre as ferramentas testadas.

NOVELETO, PEDRO G.S.; CARNEIRO, MARCELO B.; BARBOSA, PATRICIA A.; MACHADO, ALISSON R.; SAMAD, RICARDO E.; VIEIRA JUNIOR, NILSON D.; ROSSI, WAGNER de; ALMEIDA, AMELIA. Avaliação do desempenho de ferramenta de corte cerâmica texturizada na usinagem de ferro fundido cinzento. In: CONGRESSO BRASILEIRO DE ENGENHARIA DE FABRICACAO, 9., 26-29 de junho, 2017, Joinville, SC. Anais... Rio de Janeiro, RJ: Associação Brasileira de Engenharia e Ciências Mecânicas, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28558. Acesso em: $DATA.

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Abstract: O uso de fitoterápicos tem se tornado bastante popular no Brasil devido a sua vasta flora e a crença de que tudo que é natural não apresenta efeitos danosos a saúde humana. Entretanto estes produtos podem conter elementos tóxicos ou os essenciais em excesso prejudiciais ao organismo humano O objetivo deste trabalho foi analisar fitoterápicos Espinheira Santa (Maytenus ilicifolia) e Berinjela (Solanum melongena) pelo método de análise por ativação com nêutrons (NAA). As amostras de fitoterápicos foram adquiridas em drogarias na forma de cápsulas, e os seus conteúdos foram removidos das cápsulas para as análises. O procedimento de NAA consistiu em irradiar as alíquotas dos fitoterápicos e os padrões sintéticos de elementos com nêutrons do reator nuclear IEAR1 seguida de espectrometria de raios gama. Os radioisótopos formados foram identificados pelas meias vidas e energias dos raios gama e as concentrações dos elementos foram calculadas pelo método comparativo. Para controle de qualidade analítica, foram analisados os materiais de referência certificados e cujos resultados apresentaram, em geral, uma boa exatidão e precisão. Nos fitoterápicos, os elementos K e Ca foram encontrados em concentrações mais elevadas, da ordem de mg g-1, Br, Fe, Rb e Zn da ordem de μg g-1 e os elementos Co, Cr, Cs, La e Sc da ordem de ng g-1. Resultados obtidos neste trabalho demonstraram a viabilidade de aplicar o procedimento de NAA na determinação da composição elementar de fitoterápicos.

Palavras-Chave: concentration ratio; elements; gamma spectroscopy; irradiation; medicinal plants; neutron activation analysis; neutron beams

PEREIRA, LUAN M.; SAIKI, MITIKO. Análise da composição elementar dos fitoterápicos espinheira santa e berinjela pelo método de análise por ativação com nêutrons. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28447. Acesso em: $DATA.

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Abstract: O presente estudo avaliou a concentração de elementos em dois pontos do reservatório (1 e 3). Foram coletados 2 perfis de sedimentos fracionados em campo, a cada 2,5 cm, gerando 14 e 20 frações, respectivamente, de acordo com as suas profundidades (35 e 50 cm). Utilizou-se a técnica de Análise por Ativação com Nêutrons Instrumental (INAA) e foram determinadas as concentrações dos elementos: As, Ba, Br, Ca, Co, Cr, Cs, Fe, Hf, K, Na, Rb, Sb, Sc, Ta, Th, U, Zn e os elementos terras raras (Ce, Eu, Gd, La, Lu, Nd, Sm, Tb e Yb). A validação da metodologia foi feita através das análises de materiais de referência certificados. Os valores do NASC (North American Shale Composite) foram utilizados como valores de referência para cálculo de Fator de Enriquecimento (FE) e Índice de Geoacumulação (IGeo), ferramentas utilizadas para avaliação de níveis de poluição. Comparou-se também a concentração dos elementos As, Cr e Zn com os valores orientadores TEL (Treshold Effect Level) e PEL (Probable Effect Level), valores que fornecem faixas de concentração para esses elementos indicando a presença ou não de prováveis efeitos na biota aquática advinda dessas concentrações.

Palavras-Chave: calibration standards; elements; enrichment; neutron activation analysis; radioecological concentration; sediments; trace amounts; water pollution; water reservoirs

ANGELINI, MATHEUS; FRANKLIN, ROBSON L.; ROCHA, FLAVIO R.; FAVARO, DEBORAH I.T. Avaliação e distribuição de metais, elementos traço e terras raras em perfis de sedimentos do reservatório de promissão, estado de São Paulo, por INAA. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28445. Acesso em: $DATA.

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Abstract: The Cobalt-60 irradiator of IPEN / CNEN, a category IV facility, has a security system for inter locking doors or exposure of radioactive sources made simultaneously by a programmable logic controller (PLC) model S7-200 from Siemens and a relay logic. From a set of information, both systems work together opening doors or exposing the sources. All incoming and outgoing information are sent serially via EIA232 communication to a personal computer with Windows® platform for a supervisory program which provides the monitoring of the entire process by a synoptic table on the computer screen and is also intended to keep records of all events on the computer's hard drive. A deficiency was found for the process of sending events via serial communication (EIA232) from PLC to the supervisory program. When failure occurred in a very short time, the PLC always took the right decision, but the registration process that had to go through the Windows® timeshare lost the information. In the previous work [1] developed a standalone electronics unit connected to the inputs and outputs of the security system, fully optocoupled to avoid any interference to the security system that records each event on a memory card. In this work, for checking the unit developed record time ability, transients incoming signals for simulating failures, were injected at security system inputs and the response time of security system, supervisory program and the autonomous unity were measured and compared.

Palavras-Chave: comparative evaluations; computerized control systems; failures; logic circuits; monitoring; radiation protection; recording systems; security; transients

BALDACONI, RICARDO H.; COSTA, FABIO E. da. Comparative response time and fault logging with a PLC and supervisory software and a standalone unit developed for recording. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28367. Acesso em: $DATA.

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Abstract: In Brazil, the Brazilian Nuclear Energy Commission (CNEN) and Brazilian Institute of Environment and Renewable Natural Resources (IBAMA) are the agencies responsible for the execution, regulation and control of nuclear and environmental policies, respectively. Such regulatory activities are very comprehensive (IBAMA) or too specific (CNEN), revealing other aspects that would, also, need to be observed so that the management could be carried out efficiently (quality) and effectively (safety), including the three governmental administrative levels: Federal, State and Municipal. In addition to laws, regulations, decrees and resolutions, there are also national and international standards and guides that provide guidelines for structuring the current management and the use of best regulatory practices. The Brazilian Multipurpose Reactor Enterprise (RMB) is a CNEN project, complying with a Multi-Year Plan of the Brazilian Ministry of Planning, Development and Management (MPDG). The Enterprise is being developed under the responsibility of the Directorate of Research and Development - DPD of CNEN and will have a facility for treatment and initial temporary storage of the radioactive waste generated by the operation of the research reactor and the activities carried out in the associated laboratories. The RMB will be built in the city of IPERÓ, located in the state of São Paulo, near ARAMAR Experimental Center of the Brazilian Navy. This work aims to present the research results regarding the various aspects that regulate, legislate and standardize the practices proposed to the Radioactive Waste Management of the RMB project.

Palavras-Chave: construction; legal aspects; licensing; radioactive waste management; recommendations; regulations; research reactors; standards

SALVETTI, T.C.; MARUMO, J.T. Survey of legal aspects, regulations, standards and guidelines applicable to radioactive waste management of the Brazilian Multipurpose Reactor – RMB. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28365. Acesso em: $DATA.

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Abstract: Since 1983, the Sealed Source Production Laboratory at the Nuclear and Energy Research Institute has been providing products and services to the private and governmental Brazilian users of industrial radiography and nucleonic control systems. Radioactive sealed sources are commonly used in nondestructive tests as radiography to make inspections and verify the internal structure and integrity of materials and in nucleonic gauges to control level, density, viscosity, etc. in on-line industrial processes. One of the most important activities carried out by this laboratory is related to the inspection of source projectors devices used in industrial radiography and its constituent parts as well as remote handle control assembly drive cable and guide tube systems. The laboratory also provide for the users iridium-192, cobalt-60 and selenium-75 sealed sources and performs quality control tests replacing spent or contaminated radiative sources. All discard of radioactive source is treated as radioactive waste. Additionally, administrative and commercial processes and protocols for exportation and transport of radioactive material are developed by specialized departments. In this work are presented the mean processes and procedures used by the Sealed Source Production Laboratory such as the arrival of the radioactive material to the laboratory and the source projectors, mechanical inspections, source loading, source leaking tests, etc.

Palavras-Chave: cobalt 60; hot cells; industrial radiography; iridium 192; laboratories; production; sealed sources; selenium 75

SANTOS, PAULO de S.; NGUNGA, DANIEL M.G.; CAMARA, JULIO R.; VASQUEZ, PABLO A.S. Radioactive sealed sources production process for industrial radiography. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28363. Acesso em: $DATA.

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Abstract: The CANDU (Canadian Deuterium Uranium) is a nuclear reactor developed by AECL (Atomic Energy of Canada Limited). The first small-scale reactor is known as NPD and was made in 1955 and commenced operation in 1962. It is a pressurized heavy water reactor and uses D2O as moderator and coolant and therefore uses natural uranium as fuel. There have been two major types of CANDU reactors, the original design of around 500 MWe that was intended to be used in multi-reactor installations in large plants, and the rationalized CANDU6 which has units in Argentina, South Korea, Pakistan, Romania and China. Throughout the 1980s and 90s the nuclear power market suffered a major crash, with few new plants being constructed in North America or Europe. Design work continued through, however, and a number of new design concepts were introduced that dramatically improved safety, capital costs, economics and overall performance. These Generation III+ and Generation IV machines became a topic of considerable interest in the early 2000s as it appeared a nuclear renaissance was underway and large numbers of new reactors would be built over the next decade. The present work aims to study the reactors of the CANDU type, exploring from its creation to studies directed to G-III and G-IV reactors.

Palavras-Chave: calandrias; candu type reactors; capacity; design; fuel channels; fuel cycle; fuel element clusters; historical aspects; performance; spent fuels

MORAD, CESAR M.; STEFANI, GIOVANNI L. de; SANTOS, THIAGO A. dos. CANDU: study and review. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28361. Acesso em: $DATA.

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Abstract: In the present study was observed the influence of gamma radiation in thermal and mechanical properties of the experimental dental composites based on BISGMA/TEGDMA filled with pre-irradiated MMT nanoparticles (Cloisite® 20A). MMT nanoparticle was pre-irradiated at doses of 10, 15 and 70 kGy. As a control group MMT nanoparticle was added in the polymeric matrix without pre-irradiation. Four formulations of experimental nanocomposites were studied all with 50% wt of filler. The characterization of the experimental composites was performed by means of the following techniques: Thermogravimetry Analysis (TGA), Elastic Modulus and Flexural Strength. It was observed that the group filled with pre-irradiated nanoparticles at dose of 70 kGy showed a delay in the decomposition temperature when compared to the control group. For elastic modulus the results showed a proportional increase related to the dose of radiation applied in the MMT nanoparticle. Regarding flexural strength, the groups filled with pre–irradiated nanoparticles and the control group presented similar results.

Palavras-Chave: composite materials; fillers; flexural strength; fourier transformation; gamma radiation; infrared spectra; nanocomposites; nanoparticles; polymers; radiation effects; thermal gravimetric analysis; thermodynamic properties

SANTOS, TAMIRIS M.R.; CAMPOS, LUIZA M.P.; SANTOS, MARIANA de J.; BOARO, LETICIA C.; PARRA, DUCLERC F. Nfluence of radiation on the thermal and mechanical properties of BISGMA / TEGDMA based nanocomposites using pre-irradiated MMT nanoparticles as filler. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28357. Acesso em: $DATA.

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Abstract: Neodymium and its compounds are being increasingly applied in the manufacture of new materials. In nuclear area neodymium isotopes are used in a variety of scientific applications. Nd-142 has been used to produce short-lived Tm and Yb isotopes. Nd-146 has been suggested to produce Pm-147 and Nd-150 has been used to study double beta decay. Due to the several modern applications using nanomaterials, more and more highly rare earth compounds have been demanded. The researches at IPEN uses the experience gained in rare earth separation for the preparation of some pure acetates, purity > 99.9% for application in nanotechnology research. A simple and economical chemical process to obtaining neodymium acetate of high purity is studied. The raw material in the form of mixed rare earths carbonate comes from Brazilian monazite. It is used the technique of strong cationic exchange resin, proper to water treatment, to the neodymium's fractionation and it is achieved a purity of 99.9% in Nd2O3 and yield greater than or equal 80%, with the elution of rare earths by EDTA solution in pH controlled. The complex of EDTA-neodymium is transformed in neodymium oxide, subsequently the oxide is dissolved in acetic acid to obtain the neodymium acetate. The solid salt was characterized via molecular absorption spectrophotometry, mass spectrometry, thermal analysis, chemical analysis and X ray diffraction. In summary the analytical data collected allowed to conclude that the stoichiometric formula for the neodymium acetate prepared is Nd(CH 3COOH)3.1.5H2O.

Palavras-Chave: acetates; cations; chemical analysis; edta; ion exchange; mass spectroscopy; monazites; nanotechnology; neodymium; spectrophotometry; thermal analysis

QUEIROZ, C.A.S.; PEDREIRA FILHO, W.R.; SENEDA, J.A. Preparation of neodymium acetate for use in nuclear area and nanotechnology. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28355. Acesso em: $DATA.

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Abstract: The IEA-R1 research reactor works 40h weekly with 4.5 Mw power. The storage rack for spent fuel elements has less than half of its initial capacity. Under these conditions (current conditions of reactor operation 32h weekly will have 3 spend fuel by year, then, approximately 3 utilization rate Positions/year). Thus, we will have only about six years of capacity for storage. Whereas the desired service life of the IEA-R1 is at least another 20 years, it will be necessary to increase the storage capacity of spent fuel. Hence, it is necessary to double the wet storage capacity (storage in the IEA-R1 reactor's pool). After reviewing the literature about materials available for use in the construction of the new storage rack with absorber of neutrons, the BoralcanTM (manufactured by 3TMhis) wwaosr kc hporseesne,n dtsu es ttuod iitess :p r(oap) efrotrie tsh. e construction of new storages racks with double of the current capacity using the same place of current storages racks and (b) criticality analysis using the MCNP-5 code. Two American Nuclear Data Library were used: ENDF / B-VI and ENDF / B-VII, and the results obtained for each data bases were compared. These analyzes confirm the possibility of doubling the storage capacity of fuel elements burned in the same place occupied by the current storage rack attending to the IEA-R1 reactor needs and attending the safety requirements according to the National Nuclear Energy Commission - CNEN and the International Atomic Energy Agency (IAEA). To calculate the keff were considered new fuel elements (maximum possible reactivity) used in full charge of the storage rack. With the results obtained in the simulation we can conclude that doubling the amount of racks for spent fuel elements are complied with safety limits established in the IAEA standards and CNEN of criticality (keff < 0.95).

Palavras-Chave: boron; comparative evaluations; computerized simulation; criticality; fuel racks; iear-1 reactor; monte carlo method; nuclear data collections; spent fuel elements; spent fuel storage

RODRIGUES, ANTONIO C.I.; MADI FILHO, TUFIC; SILVA, DAVILSON G. da. Study and project of the new rack with boron for storage of fuel elements burned in the IEA-R1 research reactor. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28353. Acesso em: $DATA.

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Abstract: Plastic bags, packaging and furniture items are examples of plastic utilities always present in life. However, the end-of-life of plastics impacts the environment because of this ubiquity and also often their high degradation time. Recycling processes are important in this scenario because they offer many solutions to this problem. Basically, four ways are known for plastic recycling: primary recycling, which consists in re-extrusion of clean plastic scraps from a production plant; secondary recycling, that uses end-of-life products that generally are reduced in size by extrusion to obtain a more desirable shape for reprocessing (pellets and powder); tertiary recover which is related to thermo-chemical methods to produce fuels and petrochemical feedstock; and quaternary route, that is related to energy recovery and it is done in appropriate reactors. In this work, high density polyethylene (HDPE) was recovered to simulate empirically the primary and secondary recycling ways using materials which ranged from pristine to 20-fold re-extrused materials. The final 20-fold recycled thermoplastic was irradiated in an electron beam accelerator under a dose rate of 22.4 kGy/s and absorbed doses of 50 kGy and 100 kGy. The characterization of HDPE in distinct levels of recovering was performed by infrared spectroscopy (FTIR) and thermogravimetric degradation. In the HDPE recycling, degradation and crosslinking are consecutive processes; degradation is very noticeable in the 20-fold recycled product. Despite this, the 20-fold recycled product presents crosslinking after irradiation process and the post-irradiation product presents similarities in spectroscopic and thermal degradation characteristics of pristine, irradiated HDPE. These results are discussed.

Palavras-Chave: absorbed radiation doses; cross-linking; dose rates; electron beams; extrusion; fourier transformation; infrared spectra; polypropylene; recycling; shear; thermal degradation

CARDOSO, JESSICA R.; MOURA, EDUARDO de; GERALDO, AUREA B.C. Electron beam irradiation process applied to primary and secondary recycled high density polyethylene. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28351. Acesso em: $DATA.

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Abstract: Polyvinylpyrrolidone (PVP) hydrogels have been investigated as drug delivery matrices for the treatment of wounds, such as cutaneous leishmaniasis, and matrices with silver nanoparticles for chronic wounds and burns. The preparation of such hydrogels can occur by various cross-linking methods, such as gamma, chemical, physical, among others. The most feasible for wound dressings is gamma irradiation from cobalt-60, because gamma irradiation simultaneously promotes crosslinking and sterilization, leaving the wound dressing ready for use. The objective of this work was to investigate the effect on physico- chemical properties of gamma radiation on PVP hydrogel according to the radiation absorbed dose variation. The PVP hydrogels were irradiated with doses of 5, 15, 25, 35, 45, 55, 65, 75 and 95kGy at dose rate of 5 kGy/h and characterized by swelling, thermogravimetric and mechanical analysis. Results shown a favorable dose range window for processing of these hydrogels related to the application. The results showed that mechanical strength was affected at doses starting at 25 kGy.

Palavras-Chave: absorbed radiation doses; chemical properties; cobalt 60; differential thermal analysis; dose rates; fourier transformation; gamma radiation; hydrogels; infrared spectra; physical properties; pvp; radiation effects; swelling; tensile properties; thermal gravimetric analysis; wounds

OLIVEIRA, M.J.A.; VASQUEZ, P.A.S.; ALCANTARA, M.T.S.; MUNHOZ, M.M.L.; LUGAO, A.B. Effect of gamma radiation on polyvinylpyrrolidone hydrogels. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28349. Acesso em: $DATA.

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Abstract: Safety approach currently adopted by nuclear installations is built almost exclusively upon analytical methodologies based, mainly, on the belief that the properties of a system, such as its safety, are given by its constituent parts. This approach, however, doesn’t properly address the complex dynamic interactions between technical, human and organizational factors occurring within and outside the organization. After the accident at Fukushima Daiichi nuclear power plant in March 2011, experts of the International Atomic Energy Agency (IAEA) recommended a systemic approach as a complementary perspective to nuclear safety. The aim of this paper is to present an overview of the systems thinking approach and its potential use for structuring sociotechnical problems involved in the safety of nuclear installations, highlighting the methodologies related to the soft systems thinking, in particular the Soft Systems Methodology (SSM). The implementation of a systemic approach may thus result in a more holistic picture of the system by the complex dynamic interactions between technical, human and organizational factors.

Palavras-Chave: human factors; institutional factors; nuclear facilities; personnel management; safety; safety culture; sustainable development

VIEIRA NETO, ANTONIO S.; GUILHEN, SABINE N.; RUBIN, GERSON A.; CALDEIRA FILHO, JOSE S.; CAMARGO, IARA M.C. Soft systems methodology as a systemic approach to nuclear safety management. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28347. Acesso em: $DATA.

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Abstract: These austenitic stainless steel type 347 seamless thin-walled tubes are potential candidates to be used in fuel elements of nuclear power plants (as PWR – Pressurized Water Reactor). So, their metallurgical condition and mechanical properties, as the tensile strength and yield strength, normally are very restrict in demanding project and design requirements. Several full size tensile tests at room temperature and high temperature (315ºC) were performed in these seamless tubes in cold-worked condition. The results of specified tensile and yield strengths were achieved but the elongation of the tube, in the geometry of the component, could not be measured at high temperature due to unconventional mode of rupture (helical mode without separation of parts). The average value of elongation was obtained from stress-strain curves of hot tensile tests and was around 5%. The results obtained in this research show that this behavior of the full size tensile test samples of thin-walled tube (wall thickness less than 0.5 mm) in high temperature (315ºC) is due to the combination of the manufacturing process, the material (crystallographic structure and chemical composition) and the final geometry of the component. In other words, the strong crystallographic texture of material induced by tube drawing process in addition with the geometry of the component are responsible for the behavior in hot uniaxial tensile tests.

Palavras-Chave: crystal structure; elongation; microstructure; stainless steel-347; temperature range 0400-1000 k; tensile properties; tubes; yield strength

TERUI, CLARICE; LIMA, NELSON B. de. Study of tensile test behavior of austenitic stainless steel type 347 seamless thin-walled tubes in coldworked condition. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28345. Acesso em: $DATA.

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Abstract: Science and technology play a key role in helping countries increase the quality of life of their inhabitants. The development of peaceful nuclear applications offers important contribution for several fields. However, nuclear accidents are reported as factors that lead to the formation of prejudiced beliefs and attitudes against nuclear technology. The media also influence on what people believe about it. Holding prejudice against nuclear technology will lead to misconceptions and interfere with authorities’ decision on the development of new technology. There are evidences in the literature that implicit prejudices might be avoidable, reduced and even reversed. Interest in prejudice and stereotyping is currently shared by emerging disciplines such as neuroscience. The field of educational neuroscience has developed several types of implicit association tests aiming to assess implicit prejudices that individuals are consciously unaware. As far as prejudices are reported in the nuclear energy education scenario implicit measurement techniques can be an effective tool to identify and measure prejudices against nuclear technology. The Implicit Association Test (IAT) is a valuable tool used worldwide as a measurement technique to assess implicit attitude toward discriminatory behaviors. This study aims to demonstrate the design and development of a neuroscience-based methodology, which will include a future administration of the IAT to school teachers to assess their implicit associations regarding nuclear energy. The procedure will contribute for understanding implicit prejudices interfering with teaching practices. Teaching a balanced view about the applications of the nuclear technology will contribute for the acceptance of nuclear technology.

Palavras-Chave: education; f codes; learning; neurology; nuclear energy; public opinion; research programs; testing

BARABAS, ROBERTA de C.; SABUNDJIAN, GAIANE. Neuroscience applied to nuclear energy teaching. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28343. Acesso em: $DATA.

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Abstract: Os transformadores elétricos são equipamentos essenciais na distribuição de energia elétrica, pois são utilizados para o fornecimento contínuo eletricidade. Por este motivo é importante estudar as possibilidades de melhorar seus sistemas de isolamento e refrigeração. A aplicação de nanofluidos em óleos minerais isolantes, que possuem função de resfriamento e isolamento elétrico, é uma questão relevante nesta área. Neste trabalho, são comparadas as características do óleo mineral base utilizado em transformadores elétricos com amostras coloidais (nanofluidos) feitas com o mesmo óleo base utilizando-se diferentes concentrações de nanopartículas de SiO2 e TiO2. As características de condutividade térmica e resistência dielétrica do nanofluido dependem das concentrações de nanopartículas, porém o fluido deve manter todas as características de isolamento a serem usadas em transformadores elétricos. A análise será realizada através de simulações computacionais usando o software FEMM 2D, aplicando seu módulo de condutividade térmica. Os dados de entrada foram retirados da caracterização de amostras produzidas com diferentes concentrações de nanopartículas de SiO2 e TiO2 (usando o mesmo óleo mineral base). Os parâmetros foram aplicados em um modelo computacional de um transformador de 50 kVA, com geometria usual e circulação natural de óleo (por convecção) referenciando transformadores elétricos utilizados no mercado para a conversão de energia. Este artigo apresenta alguns dos resultados de um estudo das propriedades dielétricas e da condutividade térmica de um nanofluido a base de óleo mineral.

Palavras-Chave: computerized simulation; dielectric properties; f codes; lubricants; nanofluids; nanoparticles; silicon oxides; thermal conductivity; titanium oxides; transformers; viscosity

LOPES, DANIEL R.P.; OLIVEIRA, OTAVIO L. de; ROCHA, MARCELO da S. Estudo da aplicação de nanofluidos de SiO2 e TiO2 em transformadores elétricos a óleo para análise de desempenho da condutividade térmica e rigidez dielétrica. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28341. Acesso em: $DATA.

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Abstract: In this work, the structure and microstructure of Nd:KY3F10 nanoparticles was probed using X-ray synchrotron diffraction analysis. Rietveld refinement was applied to obtain cell parameters, atomic positions and atomic displacement factors to be compared with the ones found in literature. X-ray line profile methods were applied to determine mean crystallite size and crystallite size distribution. Thermoluminescent (TL) emission curves were measured for different radiation doses, from 0.10kGy up to 10.0kGy. Dose-response curves were obtained by area integration beneath the peaks from TL. The reproducibility of the results in this work has shown that this material can be considered a good dosimetric material.

Palavras-Chave: critical size; doped materials; dose-response relationships; dosimetry; nanoparticles; neodymium; radiation doses; thermoluminescence; x-ray diffraction; yttrium fluorides

ICHIKAWA, RODRIGO U.; LINHARES, HORACIO M.S.M.D.; SILVA, ANDRE S.B. da; TEIXEIRA, MARIA I.; RANIERI, IZILDA M.; TURRILLAS, XAVIER; MARTINEZ, LUIS G. X-ray diffraction analysis of KY3F10 nanoparticles doped with Nd and preliminary studies for its use in high-dose radiation dosimetry. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28339. Acesso em: $DATA.

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Abstract: Gadolinium is one of the best neutron absorber materials and its usage can be considered as a burnable poison for Light Water Reactors (LWR) and as a sacrificial material in Sodium Fast Reactor (SFR). Most of the experiments in the literature focus on nuclear fuel with up to 12 wt% Gd2O3. Recently, the phase diagram and melting point has been investigated for high contents of Gd2O3 in the U-Gd-O system, that means a solid solution of the composition (U1-x, Gdx)O2 for 0<x<100%. In this work, we present the analysis of the U-Gd-O system for high contents of Gd2O3 using X-ray diffraction data. Rietveld analysis was applied to obtain cell parameters, atomic positions and atomic displacement factors and compared with literature avaliable. Also, the quantification of phases was performed for the different contents of Gd2O3 in the system. Finally, mean crystallite sizes were determined and correlated with the weight fraction of the phases.

Palavras-Chave: atomic displacements; burnable poisons; critical size; gadolinium oxides; microstructure; mixtures; phase diagrams; uranium; x-ray diffraction

DARIN, GASPAR; IMAKUMA, KENGO; MARTINEZ, LUIS G.; TURRILAS, XABIER M.; ICHIKAWA, RODRIGO U.; SILVA, ANDRE S.B.; DURAZZO, MICHELANGELO; RIELLA, HUMBERTO G.; URANO, ELITA. Structural and microstructural analysis of the U-GD-O system using X-ray diffraction data. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28337. Acesso em: $DATA.

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Abstract: Since 2004, the Multipurpose Gamma Facility at the Nuclear and Energy Research Institute has been providing services on radiation processing for disinfection and sterilization of health care and disposable medical products as well to support research studies on modification of physical, chemical and biological properties of several materials. Recently, there was an increment in irradiation of the Cultural Heritages. This facility uses C-188 double-encapsulated radioactive Cobalt-60 sources kwon as pencils from manufactures outside of country. The activity of the cobalt sources decays into a stable nickel isotope with a half-life around 5.27 years, which means a loss of 12.3% annually. Then, additional pencils of Cobalt-60 are added periodically to the source rack to maintain the required capacity or installed activity of the facility. The manufacturer makes shipping of the radioactive sources inside a high density container type B(U) , by sea. This one involves many administrative, transport and radiation safety procedures. Once in the facility, the container is opened inside a deep pool water to remove the pencils. The required source geometry of the facility is obtained by loading these source pencils into predetermined diagram or positions in source modules and distributing these modules over the source rack of the facility. The dose variation can be reduced placing the higher activity source pencils near the periphery of the source rack. In this work are presented the procedures for perform the boiling leaching tests applied to the container, the Cobalt-60 sources installation, the loading processes and the source rack loading optimization.

Palavras-Chave: cobalt 60; gamma radiation; leaching; loading; nuclear materials management; radiation sources; sealed sources; security

SANTOS, PAULO de S.; VASQUEZ, PABLO A.S. C-188 CO-60 sources installation and source rack loading optimization processes in a gamma irradiation facility. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28333. Acesso em: $DATA.

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Abstract: The use of ultrashort pulsed lasers is an alternative for micro-machining in metal surfaces, with diverse applications in several industrial areas, such as aeronautics, aerospace, naval, nuclear, among others, where there is a growing concern with reliability in service. In this work, micro-machining were performed on titanium surfaces using femtosecond ultrashort pulses. Such a process resulted in minimal heat transfer to the material, thus avoiding and surface deformation of the titanium plate and the formation of resolidified material in the ablated region, which are drawbacks present in the use of the long pulsed keyed laser of the order of nanoseconds. Three types of micro-machining were performed, with variations in the distances between the machined lines. It was also verified that the wettability increases when there is an increase in the distance between machined lines. Finally, in order to change the surface with minimal removal of material, it has been found that the use of ultra-short pulse lasers provide great benefits for the integrity of the ablated material. This initial study is the starting point for the study of other metals, such as Maraging Steels and Zircaloy that will be the target of future work.

Palavras-Chave: ablation; laser radiation; machining; pulsed irradiation; pulses; titanium; wettability

NOGUEIRA, ALESSANDRO F.; SAMAD, RICARDO E.; VIEIRA JUNIOR, NILSON D.; ROSSI, WAGNER de. Study of ablation on surfaces of nuclear-use metals irradiated with femtosecond laser. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28331. Acesso em: $DATA.

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Abstract: This study proposes the application of Eichhornia crassipes roots biomass to remove cobalt and zinc ions from solution, aiming its application to effluent treatment. The efficiency of adsorption and the percent of removal were checked as a function of pH and contact time. The plants, for biomass production, were collected at the Billings reservoir in São Bernardo do Campo, located in the Southeast of São Paulo Metropolitan Region. The biomass obtained was subjected to the chemical activation process by the treatment with HCl 0.1 molL-1 in order to increase its surface area. The concentrations of cobalt and zinc, present in the adsorbent, before and after the adsorption experiments were determined by the instrumental neutron activation analysis (INAA) technique. Results showed that the pH of the solution must be adjusted after the addition of the biomass. The contact time for maximum removal of both ions is between 20 and 30 min.

Palavras-Chave: adsorption; aqueous solutions; biomass; cobalt ions; concentration ratio; liquid wastes; neutron activation analysis; ph value; removal; zinc ions

OLIVEIRA, JULIANA de A.S.; SILVA, PAULO S.C. da. Use of macrophites for removal of Co e Zn in liquid effluents. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28329. Acesso em: $DATA.

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Abstract: The degree of radiosensitivity depends mostly on the species, the stage of the embryo at irradiation, the doses employed and the criteria used to measure the effect. One of the most common criteria to evaluate radiosensitivity in seeds is to measure the average plant production. Dry soya seeds were exposed to low doses of gamma radiation from source of Cobalt-60, type Gammecell-220, at 0.210 kGy dose rate. In order to study stimulation effects of radiation on germination, plant growth and production. A treatment with four radiation doses was applied as follows: 0 (control); 12.5; 25.0 and 50.0 Gy. Seed germination and harvested of number of seeds and total production were assessed to identify occurrence of stimulation. Soya seeds number and plants were handled as for usual seed production in Brazil. The low doses of gamma radiation in the seeds that stimulate the production were the doses of 12.5 and 50.0 Gy. The results show that the use of low doses of gamma radiation can stimulate germination and plant production.

Palavras-Chave: cobalt 60; gamma radiation; germination; harvesting; low dose irradiation; radiation doses; radiation effects; radiosensitivity; soybeans

FRANCO, JOSE G.; FRANCO, SUELY S.H.; FRANCO, CAIO H.; ARTHUR, VALTER; ARTHUR, PAULA B.; VILLAVICENCIO, ANNA L.C. Low doses of gamma radiation in soybean. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28325. Acesso em: $DATA.

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Abstract: Brazil is currently planning to produce 99Mo from fission of LEU targets to meet the present national demand of 99m Tc. The 99Mo activity planned at the end of irradiation is 5000 Ci (185 TBq) per weekly cycle, in order to meet the present demand of 1000 Ci (37 TBq) per week, after target cooling and processing. To predict the activities that will be handled in the waste treatment facility, the computational code SCALE 6.0 was used to simulate the irradiation of the uranium targets and the decay of radioactive products. This study presents the findings of this research, mainly focused on the actinides activity that will be present in the waste and the respective radioactive decay pattern over a period of one hundred thousand years.

Palavras-Chave: actinides; computerized simulation; daughter products; irradiation; molybdenum 99; radioactive wastes; radioactivity; s codes; uranium 235 target

HIROMOTO, GORO; DELLAMANO, JOSE C. Radioactive decay pattern of actinides present in waste from Mo-99 production. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28323. Acesso em: $DATA.

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Abstract: Wounds from stinging freshwater stingrays are painful, difficult to heal and cause extensive necrosis and systemic phenomena. The treatment is symptomatic, of low efficiency and there is no therapy, which causes more suffering to the injured. This study aimed to evaluate the immune response induced by the native or irradiated by 60-Co gamma from Paratrygon aiereba mucus. IPEN’s Committee on Ethics in the Use of Animals (n.º126/2013) and lanes captured under license from the Chico Mendes Institute for Biodiversity Conservation (n.º6781-1/2014) approved this research. For the assays, sera from Swiss mice previously immunized against native or irradiated mucus were used. The proliferation of splenic B cells in response to mucus was evaluated by the In Vitro Induced Antibody Production method and serum and splenic cytokines were also quantified. Our data demonstrate that the irradiated mucus of P. aiereba induces greater production of antibodies and more immunological memory in the mice. Spleen cells from animals immunized against irradiated mucus produced IFN-γ, TNF-α and IL-10, and serum TNF-α (immunized group against irradiated mucus) and IL-6 and IL-17 (immunized group against native mucus). The results corroborate the use of ionizing radiation, with production of highly responsive antibodies and better immune response, besides proving that Paratrygon aiereba mucus is capable of stimulating cellular and humoral adaptive immune response, contributing to the continuity of associated investigations.

Palavras-Chave: antibodies; cobalt 60; fishes; immune serums; immunity; ionizing radiations; lymphokines; mice; spleen cells; venoms; wounds

THOMAZI, GABRIELA O.C.; COSTA, ANDREA da; RODRIGUES, JAQUELINE P.; ALVES, GLAUCIE J.; TURIBIO, THOMPSON de O.; ROCHA, ANDRE M.; AIRES, RAQUEL da S.; JACOME, LARISSA B.S.; SEIBERT, CARLA S.; SPENCER, PATRICK J.; GALISTEO JUNIOR, ANDRES J.; ANDRADE JUNIOR, HEITOR F. de. Previous 60-CO radiation from Paratrygon aiereba mucus induces the production of highly responsive antibodies and a better immune response in mice. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28321. Acesso em: $DATA.

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Abstract: This study aims to characterize the artificial peloid obtained by maturing bentonite with Águas de Lindóia water for periods of three, six and nine months. The pH, moisture, organic matter content, loss on ignition and swelling power of matured and non-matured samples were measured for physicochemical characterization. The elemental concentration was determined by instrumental neutron activation analysis. Results showed that water adsorption capacity, organic matter and swelling power is related to the maturation time and no significant differences occurs in the elemental concentration except for Na.

Palavras-Chave: adsorption; bentonite; concentration ratio; elements; irradiation; maturation; mineral springs; moisture; neutron activation analysis; neutron flux; organic matter; ph value; sediments; swelling

TORRECILHA, JEFFERSON K.; SILVA, PAULO S.C. Bentonite maturation with “Águas de Lindóia” water (SP). In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28319. Acesso em: $DATA.

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Abstract: In this study optimization of procedures and standardization of Instrumental Neutron Activation Analysis (INAA) method were carried out for the determination of the elements bromine, chlorine, magnesium, manganese, potassium, sodium and vanadium in biological matrix materials using short irradiations at a pneumatic system. 2k experimental designs were applied for evaluation of the individual contribution of selected variables of the analytical procedure in the final mass fraction result. The chosen experimental designs were the 23 and the 24, depending on the radionuclide half life. Different certified reference materials and multi-element comparators were analyzed considering the following variables: sample decay time, irradiation time, counting time and sample distance to detector. Comparator concentration, sample mass and irradiation time were maintained constant in this procedure. By means of the statistical analysis and theoretical and experimental considerations, it was determined the optimized experimental conditions for the analytical methods that will be adopted for the validation procedure of INAA methods in the Neutron Activation Analysis Laboratory (LAN) of the Research Reactor Center (CRPq) at the Nuclear and Energy Research Institute (IPEN – CNEN/SP). Optimized conditions were estimated based on the results of z-score tests, main effect, interaction effects and better irradiation conditions.

Palavras-Chave: biological materials; concentration ratio; elements; experimental data; high-purity ge detectors; neutron activation analysis; optimization; standardization; validation

SANTOS, UANDA P. de M. dos; MOREIRA, EDSON G. Experimental design technique applied to the validation of an instrumental neutron activation analysis procedure. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28317. Acesso em: $DATA.

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Abstract: Edible flowers are increasingly being used in gastronomy, being also recognized for their potential valuable effects beneficial to human health. Viola tricolor L. (johnny-jump-up) flowers represents one of the most popular and are widely used in culinary preparations, being also acknowledged for their antioxidant properties. To improve the conservation and safety of flowers the new approaches can be used as ionizing radiation. Radiation treatment contribute to the improve the safety, quality and extends the shelf life of foods by disinfestation insects and reducing or eliminating pathogenic microorganisms. The purpose of this study was to evaluate the dose-dependent effects of electron beam and gamma irradiation in the doses of 0.5, 0.8, 1.0 kGy and control (non-irradiated) on the antioxidant activity of Viola tricolor L.by the Oxygen Radical Absorbance Capacity assay (ORAC). Therefore, the ionizing radiation did not affect the antioxidant activity of the flowers.

Palavras-Chave: antioxidants; cobalt 60; dose rates; electron beams; flowers; gamma radiation; radiation effects; radicidation

KOIKE, AMANDA C.R.; SILVA, PAMELA G. da; RODRIGUES, FLAVIO T.; ALENCAR, SEVERINO M. de; VILLAVICENCIO, ANNA L.C.H. Analysis on antioxidant activity by orac method in viola tricolor L. flowers processed by ionizing radiation. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28315. Acesso em: $DATA.

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Abstract: The objective of this work was to determine the kinetic parameters of BeO thermoluminescent (TL) samples. The knowledge of the kinetic parameters is important for the general description of the physical characteristics of a thermoluminescent material. Using a linear heating rate of 5K/s-1, the BeO peak temperatures obtained were (474.7 ± 1.2) K and (620.5 ± 1.2) K, respectively, for the first and second TL peaks. The peak shape and the glow curve area measurement methods and the Urbach formula have been used for the trap parameter determination. A kinetic order of about two was determined for the first peak, whereas the second peak followed the first-order kinetics according to the geometrical factor. The energy activation values obtained using different kinds of measurements are in good agreement, including the Kitis method for deconvolution of the glow curve. Furthermore the results agree with those presented by other authors.

Palavras-Chave: activation energy; beryllium oxides; glow curve; impurities; peaks; thermoluminescence

ALGARVE, FABIO J.; CALDAS, LINDA V.E. Determination of the kinetic parameters of BeO thermoluminescent samples using different methods. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28313. Acesso em: $DATA.

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Abstract: Aquatic ecosystems are directly affected by contaminants, such as, toxic elements that do not remain in sediment in a insoluble form. Anthropogenic and natural actions influence sediment dynamics that could lead to a potential contaminant accumulation. Therefore, to evaluate possible environmental impacts is,in many cases, mandatory. Environmental impact assessment studies are a licensing toolthat seeks to control degradation activities, taking into account the legal and regulatory provisions and technical standards applicable to the case. The present study aims to evaluate the sediment quality in the area of influence of the Brazilian Multipurpose Nuclear Reactor (RMB) to be installed in the contiguous area of the Experimental Center of Aramar of the Technological Center of the Navy in São Paulo (CTMSP), located in the city of Iperó - SP. The potentially toxic elements As, Cd and Hg were analyzed by Graphite Furnace Atomic Absorption Spectrometry (GFAAS) and Cr, Cu, Ni and Zn by Inductively Coupled Plasma Optical Emission Spectrometry (ICP-OES). Results were compared with Canadian Council of Ministers of the Environment (CCME) guideline values (TEL and PEL) and the maximum permitted values of Resolution 454/12. These toxic elements (As, Cd, Hg, Cr, Cu, Ni and Zn) were found below maximum allowed concentrations from national and international legislation. This study provides support for RMB post-completion evaluations, in order to prevent these elements to exceed tolerated levels, ensuring ecological, social and economic values.

Palavras-Chave: absorption spectroscopy; aquatic ecosystems; concentration ratio; contamination; ecological concentration; elements; environmental impacts; reactors; rivers; sediments; toxic materials; toxicity

SILVA, TATIANE B.S.C. da; STELLATO, THAMIRIS B.; MONTEIRO, LUCILENA R.; MARQUES, JOYCE R.; FAUSTINO, MAINARA G.; SANTOS, CAMILA F.R.T.T.; OLIVEIRA, CINTIA C. de; MIRANDA, GABRIELLE S.; PIRES, MARIA A.F.; COTRIM, MARYCEL E.B. Toxic elements in sediment from two water bodies near Brazilian Multipurpose Reactor – RMB installation area. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28311. Acesso em: $DATA.

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Abstract: The greatest impact of the tomography technology application currently occurs in medicine. The great success of medical tomography is due to the human body presents reasonably standardized dimensions with wellestablished chemical composition. Generally, these favorable conditions are not found in large industrial objects. In the industry there is much interest in using the information of the tomograph in order to know the interior of: (i) manufactured industrial objects or (ii) machines and their means of production. In these cases, the purpose of the tomograph is to: (a) control the quality of the final product and (b) optimize production, contributing to the pilot phase of the projects and analyzing the quality of the means of production. In different industrial processes, e. g. in chemical reactors and distillation columns, the phenomena related to multiphase processes are usually fast, requiring high temporal resolution of the computed tomography (CT) data acquisition. In this context, Instant non-scanning tomograph and fifth generation tomograph meets these requirements. An instant nonscanning tomography system is being developed at the IPEN/CNEN. In this work, in order to optimize the system, this tomograph comprised different collimators was simulated, with Monte Carlo method using the MCNP4C. The image quality was evaluated with Matlab® 2013b, by analysis of the following parameters: contrast to noise (CNR), root mean square ratio (RMSE), signal to noise ratio (SNR) and the spatial resolution by the Modulation Transfer Function (MTF(f)), to analyze which collimator fits better to the instant nonscanning tomography. It was simulated three situations; (i) with no collimator; (ii) ?25 mm x 50 mm cylindrical collimator with a septum of ø5.0 mm x 50 mm; (iii) ø25mm x 50 mm cylindrical collimator with a slit septum of 24 mm x 5.0 mm x 50 mm.

Palavras-Chave: collimators; computerized tomography; image processing; monte carlo method; quality assurance; quality management; shielding; signal-to-noise ratio; spatial resolution

VELO, ALEXANDRE F.; CARVALHO, DIEGO V.; ALVAREZ, ALEXANDRE G.; HAMADA, MARGARIDA M.; MESQUITA, CARLOS H. Reconstructed image quality analysis of an industrial instant non-scanning tomography system with different types of collimators by the Monte Carlo Simulation. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28309. Acesso em: $DATA.

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Abstract: The results of one of the recovery stages of 131I as a byproduct of the 99Mo fission production process are presented in this work. A modified wet-distillation apparatus was used for iodide purification and some work parameters were tested. The assays included iodide anion eluent, concentration of H2SO4, H2O2, the catalyst effect of MoO3, temperature and time process. The results of eluting anions demonstrated lower recovery of 131I using nitrate salt. The sulfate solution and its respective acid (H2SO4) at concentration 1.6 M, presented better results. Hydrogen peroxide was used as a main oxidant of the ions iodide, the experiments realized with 6 mL of H2O2 3% showed higher recovery than assays prepared with H2O2 higher and lower amount. Molybdenum oxide was evaluated as catalyst of iodine in solution; however, the results did not demonstrate an advantage in relation to its absence. In addition, the recovery of iodide was delayed at initial periods of the process in presence of the catalyst, leading to an increase on time process. Temperature decrease of distillation solution from 80 to 50 °C showed advantageous since the recovery yields were similar beside a lower wet drag to trap solution. Time distillation was carried out at least four hours with sampling each hour; the best times were between 1 and 2 hours. Shorter periods of distillation avoid dilution of the capture solution on the further recovery process. Several parameters were studied and it was possible to set up system that provided 131I recovery around 50% yield.

DAMASCENO, MARCOS O.; BALOGH, TATIANA S.; FORBICINI, CHRISTINA A.L.G. de O. Recovery of 131I from fission 99Mo production process by distillation method. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28307. Acesso em: $DATA.

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Abstract: In this work, two uranium silicide powdered samples, containing 67% and 42 mol% of Si, were analyzed using X-ray diffraction (named as 67Si and 42Si). For structural characterization, Rietveld refinement was used to estimate cell parameters, volume fraction (weight percent) of crystalline phases and atomic positions. For the main phases, X-ray line profile analysis (XLPA) was used to estimate mean crystallite sizes and microstrains. The 67Si sample presents higher content of USi2 (tetragonal) and the 42Si sample presents higher content of U3Si2 (tetragonal) as identified and calculated from the XRD profiles. Overall there are no appreciable structural changes and the parameters refined are in good accordance with the ones reported in the literature. Mean crystallite sizes determined by XLPA revealed small crystallites of the order of 101 nm and low microstrain for all samples.

Palavras-Chave: crystal structure; microstructure; nuclear fuels; powders; stoichiometry; uranium silicides

ICHIKAWA, RODRIGO U.; GARCIA, RAFAEL H.L.; SILVA, ANDRE S.B. da; TURRILLAS, XAVIER; SALIBA-SILVA, ADONIS M.; LIMA, NELSON B.; MARTINEZ, LUIS G. Structural and microstructural characterization of U3Si2 nuclear fuel using X-ray diffraction. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28305. Acesso em: $DATA.

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Abstract: In conventional gamma-ray spectrometry, the probability of pile-up effects is considered to be proportional to the dead-time, and is usually neglected for low dead-times (below 4-5%). In gamma-gamma coincidence spectrometry, though, while the dead time takes into account only events that are actually digitized, the pile-up effects are proportional to the actual gamma-ray detection rate in each detector, not only to the ones that trigger the coincidence gate. Thus, the pile-up corrections may not be so easy to assess as in single spectrometry systems. In this work, a system composed of two HPGe detectors coupled to a CAEN v1724 digitizer is studied. A 3kBq 60Co source was analyzed, both alone and in the presence of other radioactive sources (137Cs, 133Ba and 152Eu), and the resulting coincidence peak areas were compared to assess the effectiveness of two distinct corrections: a simple normalization by the live time of acquisition and the normalization by the count rate obtained using a pulse generator. The results obtained stress the need to use the pulse generator in this specific setup in order to get accurate results.

Palavras-Chave: barium 133; cesium 137; cobalt 60; corrections; data acquisition; dead time; digitizers; europium 152; gamma radiation; high-purity ge detectors; pulse pileup

RIBEIRO JUNIOR, IBERE S.; ZAHN, GUILHERME S.; GENEZINI, FREDERICO A. Pile-up correction for coincidence counting using a CAEN 1724 digitizer. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28303. Acesso em: $DATA.

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Abstract: This work aims to present the radioactive impurities gamma rays emitters detected in some radiopharmaceuticals widely applied to diagnosis and therapy purposes, supplied to nuclear medicine services in Brazil by the Radiopharmaceutical Center(CR) of Nuclear and Energy Research Institute, IPEN, in São Paulo. The analysis was undertaken by means of an HPGe gamma spectrometer. The radiopharceuticals analyzed were: 111In, 201Tl, 177Lu and 99mTc.

Palavras-Chave: concentration ratio; gamma radiation; high-purity ge detectors; impurities; indium 111; lutetium 177; monte carlo method; quality control; radiopharmaceuticals; technetium 99; thallium 201

KOSKINAS, MARINA F.; ALMEIDA, JAMILLE da S.; MOREIRA, DENISE S.; SEMMLER, RENATO; DIAS, MAURO da S. Gamma-ray impurities of 111In, 201Tl, 177Lu and 99mTc determined by means of a HPGE spectrometer. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28301. Acesso em: $DATA.

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Abstract: In recent years, there has been an increasing interest in finding new fast scintillating material or improve the characteristics of known scintillators for the demand of high energy physics, industrial and nuclear medical applications. Ions divalent lead Pb2+ built in some crystal structures are efficient emission centers and their applications in scintillators was and still is the reason of an intensive study of emission properties of different compounds containing these ions. The aggregation of impurities in CsI is poorly studied. The problem of impurity aggregation in CsI is of interest from point of view of the luminescent properties modification of this scintillation material. In this context, the crystals of Pb2+ doped CsI matrix were grown by the vertical Bridgman technique and subjected to annealing in vacuum of 10-6 mbar and continuous temperatura of 350°C, for 24 hours, and then they were employed. To evaluate the response of the CsI:Pb scintillator crystal to gamma radiation, radioactive sources of 137Cs (662 keV), 60Co (1173 keV and 1333 keV), 22Na (511 keV and 1275 keV) and 133Ba (355 keV) was used. The operating voltage of the photomultiplier was 2700 V for the detection of gamma rays and the accumulation time in the counting process was 600 s. The crystals used in gamma spectroscopy were cut with dimensions of 20 mm in diameter and 20 mm in height. The scintillator response to neutron radiation from a radioactive source of Am/Be with energy range of 1 MeV to 12 MeV was available. The activity of the AmBe source was 1Ci Am. The fluency was 2.6 x 106 neutrons / second. The operating voltage of the photomultiplier tube was 1300 V. The accumulation time in the counting process was 600 s. The scintillator crystals were cut with dimensions of 20 mm diameter and 10 mm height. With the results obtained, it may be observed that the crystals are sensitive to these radiations.

Palavras-Chave: annealing; barium 122; bridgman method; cesium 137; cesium iodides; cobalt 60; crystals; doped materials; gamma radiation; gamma spectroscopy; lead; sodium 22

PEREIRA, MARIA da C.C.; MADI FILHO, TUFIC; BERRETTA, JOSE R.; TOMAZ, LUCAS F.; PINTO, MARLENE C. Characteristics of Pb2+ doped CsI matriz under gamma and neutron excitations. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28299. Acesso em: $DATA.

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