Nuclear Engineering Institute

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    "20140326154755_IPCAM"

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    General simulated scenes These scenes followed a pre-defined script (see the Thesis for details), with common movements corresponding to general experiments. People go to or stand still in front of "J9", and/or go to the side of Argonauta reactor and come back again. The first type of movement is common during Irradiation experiments, where a material sample is put within the "J9" channel; and also during neutrongraphy or gammagraphy experiments, where a sample is placed in front of "J9". Here, the detailed movements of putting samples on these places were not reproduced in details, but only the whole bodies' movements were simulated (as crouching or being still in front of "J9"). The second type of movement may occur when operators go to the side of Argonauta to verify some operational condition. - Scene 2: Comprises one of the scenes with two persons. Both of them use clothes of dark colors. Both persons go to the side of Argonauta reactor and then come back and go out. Video file labels: "20140326154755_IPCAM": recorded by the left camera.Comprises one of the scenes with two persons. Both of them use clothes of dark colors. Both persons go to the side of Argonauta reactor and then come back and go out

    Solution of the Spatial Kinetic Equations Using the Expansion in Pseudo-Harmonics: cases 1d and 2d

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    Recently was demonstrated that the steady-state fixed source problems, usually represented by a non homogeneous linear system of equations, can be solved by the method of the pseudo-harmonics. The method of the pseudo-harmonics is based on the eigenfunctions associated with the leakage and removal matrix operator of the neutron diffusion equation. In this case the fixed source problem was solved considering that the neutron flux can be expanded in these eigenfunctions. The method of the pseudo-harmonics was just summarized in the determination of the coefficients of the expansion of the neutron flux, substituting like this an scheme of numeric inversion of the matrix of the linear system, usually employee in this problem type. The present work has as objective of study the possibility of to apply the method of the pseudo-harmonic in the solution of the linear system, which appears starting from the discretization of the equations of the spatial kinetic. For so much the same basic idea used in the solution of the fixed source problem was adopted now for the spatial kinetic. The method was tested for the cases 1D and 2D, formulated to leave of the discretization in finite differences of the kinetic spatial equations. The method showed good results when compared with the direct method

    Development of a methology to minimizing Am-241 waste from radioactive lightning rod

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    In 1989, the Brazilian National Nuclear Energy Commission, CNEN, cancelled the authorization to produce and install lightning rods that employed radioisotopes sources, which since then have been collected and treated as radioactive waste. The main radioisotopes employed as a radioactive source onto the lightning rods were the 241Am and 226Ra, being the 241Am the most used due to its lower production cost. In the radioactive lightning rods the sources are first fixed in a stainless steel support, then sealed and fixed on the 30 cm length lightning rod body by rivets. These captors when constantly exposed to rain and winds can release the radioactive material and then contaminate the device, generating a greater volume of waste.The focus of this preliminary study is to develop a methodology to minimize the final volume of waste by removing the source followed by a chemical treatment to clean the lightning rods. Ultrasound techniques associated with suitable solvents as water, acids and chelates was applied. Gamma spectrometry was used to analyze the material after each decontamination step. In agreement to Regulations of Radiological Protection, the results indicate that it is possible to dispose of the lightning rod after the source removal followed by a suitable treatment and reducing this way the volume of waste

    Flow injection Uranium and Zirconium determination

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    A chemical quality control of nuclear materials by Flow Injection Analysis (FIA) system for uranium and zirconium determination in presence one of each with no prior separation is presented. This method is based on a colorimetric reaction between Arsenazo III and U(IV) and Zr(IV), producing an Arsenazo III-U(IV) and Arsenazo III-Zr(IV) complexes in a strongly acid medium. Although Arsenazo III is not a specific reagent for uranium, high selectivity can be ensured in a strongly acid medium (Figure 1), when in the oxidation state

    Projeto e desenvolvimento de um sistema de irradiação multipropósito com diagnóstico de feixes para o acelerador de partículas cíclotron CV 28

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    O projeto e desenvolvimento de uma nova linha de feixe dotada de um sistema que viabilize a irradiação no Cíclotron CV-28 do Instituto de Engenharia Nuclear de alvos extensos e de geometria variável tornaram-se necessário para a realização de estudos e desenvolvimento de aplicações de técnicas nucleares e análises de materiais por ativação em condições de irradiação até então não disponíveis. Este sistema que poderá ser utilizado em irradiações com feixes de prótons, alfas, deutério e hélions (He3) a energias variáveis, é composto por dispositivos de: proteção, interceptação, colimação e medição da intensidade do feixe, de forma a possibilitar a realização de irradiações em condições controláveis e reprodutíveis. Para tanto, peças em alumínio e PVC-foram usinadas de forma a construir os componentes do sistema, notadamente colimadores com 13mm e 9mm de diâmetro, um dispositivo de colimação de quatro setores, um "beam stop", duas flanges de isolamento elétrico e um porta alvo (com janela degradadora). Identificou-se também a necessidade de se dotar o sistema aqui desenvolvido de um circuito de refrigeração próprio à água deionizada que é responsável pela refrigeração de todos os seus componentes que possam ter contato com o feixe. O sistema conta ainda com conexões para vácuo, que possibilitam fazer um pré-vácuo em sua câmara de irradiação, de forma que a mesma possa interligada a linha de transporte de feixe de Cíclotron CV-28, sem causar danos ao vácuo do mesmo. A condição para se fazer esta interligação é a obtenção de um pré-vácuo no ordem de 10-4 torr. Os resultados experimentais obtidos com a realização de irradiações de alvos metálicos especialmente desenvolvidos para testar o sistema, que é tema da presente dissertação, atestam a confiabilidade e reprodutibilidade das condições de irradiação, o que viabilizam o desenvolvimento e emprego de novas unidades de irradiação a serem incorporadas ao mesmo. Esse sistema de irradiação já está sendo utilizado na linha 2 do CV-2

    Estudo da aplicação de realidade virtual em programas de treinamento sobre a tecnologia nuclear

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    The activities developed in the units which organize the National Nuclear Energy Commission (CNEN) are present in various sectors of the Brazilian society, being them in medicine, industry, electricity generation, mining, and among the others. Based on the assumption that the employees are CNEN´s mayor differential and the training programs play an important role in the process of organizational development, because they align the professionals with the strategies of the institution properly. Focusing on these matters, this master´s thesis aimed to evaluate the training programs which are applied by CNEN, in order to propose and evaluate the use of the Virtual Reality (VR) expertise as a new method to be applied in the training programs. To accomplish this purpose, we performed two methodological approaches through questionnaires. And from the analysis of the results obtained, we could realize that there was no efficient training program which is systematically applied by CNEN, and the use of the RV technique improves the training programs in the understanding of themes whose assimilation is challengeable, such as those related to nuclear power. In this sense, for a better functional performance, the training programs adopted by CNEN must be structured so as to enable the development of each server´s skills as well as abilities and, it is actually hoped that the virtual reality tools could be inserted in these programs to pursue only this purpose.As atividades desenvolvidas nas unidades que compõem a Comissão Nacional de Energia Nuclear (CNEN) estão presentes em diversos setores da sociedade brasileira, seja na medicina, indústria, geração elétrica, mineração entre outras. Partindo do pressuposto de que os servidores são o grande diferencial da CNEN, os programas de treinamento têm papel importante no processo de desenvolvimento organizacional, pois estes alinham os profissionais com as estratégias da instituição. Nesse sentido, essa dissertação de mestrado teve como objetivo avaliar programas de treinamento aplicados pela CNEN e propor e avaliar a utilização da técnica de Realidade Virtual (RV) como um novo método a ser aplicado em programas de treinamento. Para alcançar este objetivo realizamos duas abordagens metodológicas, por meio de questionários e a partir da análise dos resultados pudemos concluir que não houve um programa de treinamento eficiente e aplicado de forma sistemática pela CNEN e que a utilização da técnica de RV valoriza os programas de treinamento na compreensão de temas de difícil assimilação, como o nuclear. Desta forma, para um bom desempenho funcional, os programas de treinamento adotados pela CNEN devem estar estruturados de forma a propiciar o desenvolvimento de competências e habilidades de seus servidores e espera-se que as ferramentas de realidade virtual sejam inseridas nestes programas para este fim

    Definição dos requisitos de posicionamento da sala de controle principal e de emergência em um reator nuclear de pesquisa

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    This work aims to define and evaluate the positioning requirements of the main control room and the emergency control room in the building where is located the nuclear research reactor. This study raises and measures the existing literature the main references regarding standards of control rooms of projects, human factors engineering, 3D modeling of nuclear plants and safety analysis reports. The literature review was used in the initial definition of requirements that impact the positioning between the main control room and emergency control room. From this initial setting, through a questionnaire, assisted experts in the validation of the main requirements to be used in the positioning of these control rooms in the building of a nuclear research reactor. As a case study, using the requirements validated by experts, the 3D modeling was implemented through Sketchup software, the nuclear reactor building, including the main control room and the emergency control room. Later, using the Pathfinder software, emergency evacuational simulations of the main control room operators to the emergency control room and to the exit of the building were carried out in order to evaluate the importance of the criteria chosen in security nuclear facility. The results indicate that the developed method allows the definition of objective criteria for the relative positioning between the main control room and emergency control room in nuclear reactor projects.Este trabalho visa definir e avaliar os requisitos de posicionamento da sala de controle principal e de emergência no prédio onde está localizado o reator nuclear de pesquisa. O presente estudo levanta e avalia na literatura existente as principais referências com relação as normas de projetos de salas de controles, engenharia de fatores humanos, modelagem 3D de plantas nucleares e relatórios de análise de segurança. A revisão da literatura foi utilizada na definição inicial dos requisitos que impactam no posicionamento entre a sala de controle principal e de emergência. A partir dessa definição inicial, através de um questionário, especialistas auxiliaram na validação dos principais requisitos que devem ser utilizados no posicionamento dessas salas de controle no prédio de um reator nuclear de pesquisa. Como estudo de caso, utilizando os requisitos validados pelos especialistas, foi implementada a modelagem tridimensional, através dos software sketchup, do prédio do reator nuclear, incluindo a sala de controle principal e a sala de controle de emergência. Posteriormente, com o uso do software Pathfinder, simulações de retirada de emergência dos operadores da sala de controle principal até a sala de controle de emergência e até a saída do prédio foram realizadas, com o objetivo de avaliar a importância dos critérios escolhidos na segurança da instalação nuclear. Os resultados obtidos indicam que o método desenvolvido permite a definição de critérios objetivos para o posicionamento relativo entre as salas de controle principal e de emergência em projetos de reatores nucleares

    "20140327180749_IPCAM"

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    Scenes for Spectrography experiment Scenes were recorded following the tasks involved in spectrography experiments, which are carried out in front of "J9" output radiadion channel, the latter in open condition. These tasks may be executed by one or two persons. One person can do the tasks, but requiring him to crouch in front of "J9" to adjust the angular position the experimental appartus (a crystal to bend the neutron radiation to the spectograph), and then to get up to verify data in a computer aside; these movements are repeated until achieving the right operational conditions. Two people may aid one another in such a way one remais crouched while the other remains still in front of the computer. They may also interchange tasks so as to divide received doses. Up to now, there are available two scenes with one person and one scene with two persons. These scenes are described in the sequel: - Scene 2: Another take similat to Scene 1. Video file labels: "20140327180749_IPCAM": recorded by the right camera.Comprises one of the scenes with one person performing spectography experiment

    Nuclear Plants and Emergency Virtual Simulations based on a Low-cost Engine Reuse

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    Our industrialised society comprises many industrial processes that are very important for everyone, in a wide range of fields. Activities related to these industrial processes, though, involve, in higher or lower degrees, some risk for personnel,  besides risk for the general public in some cases. Therefore, efficient training programs and simulations are highly required, to improve the processes involved, increasing safety for people. To cite an example, nuclear plants pose high safety requirements in operational and maintenance routines, to keep plants in safe operation conditions and reduce personnel exposure to radiation dose. Besides operational and maintenance in nuclear plants, there are also other situations where efficient training is required, as in evacuation planning from buildings in emergency situations. Also, rescue tasks play similar role. These apply specially for nuclear sites. Another situation that requires efficient training is security, what has special meaning for plants that involve dangerous materials, such as nuclear plants. Nuclear materials must be kept under high security level, to avoid any misuse

    20140402150657_IPCAM

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    Real operation scene This scene was recorded during a real Irradiation operation, more specifically during its final tasks (removing the irradiated sample). This scene was an extra recording to the script and planned ones. - Scene: Involved a number of persons, as: two operators, two personnel belonging to the radiological protection service, and the "client" who asked for the irradiation. Video file labels: "20140402150657_IPCAM": recorded by the right camera.Involved a number of persons, as: two operators, two personnel belonging to the radiological protection service, and the "client" who asked for the irradiation

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