ANA CECILIA DE SOUZA LIMA

ANA CECILIA DE SOUZA LIMA

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Study of the demand-supply for radiopharmaceuticals in IPEN
2019 - MUTARELLI, RITA de C.; LIMA, ANA C. de S.; SABUNDJIAN, GAIANE
Radiopharmaceuticals are unique medicinal formulations containing radioisotopes and are used in nuclear medicine for diagnosis and/or therapy for chronic diseases such as cancer, alzheimer and cardiac disorders. The increase in the incidence of these diseases in the Brazilian population and the trend of increasing demand for radiopharmaceuticals motivated the elaboration of this work from a system dynamics perspective. The aim of this paper is to present a System Dynamic Model for simulating the interaction between demand, capacity, workforce and production of radiopharmaceuticals produced by IPEN. The validity of this model is verified by running in Vensim PLE software using historical data. The model was based on the generic structure of commodity markets and main variables were considered to represent the market polices. The preliminary model presented was able to capture the expected behavior of the industry of radiopharmaceuticals. Two alternative scenarios were developed, one to analyze the impacts of investment in infrastructure of IPEN and the other to investigate the workforce investment. As result, the model performed well in representing the behavior of the market. In addition, scenario tests showed that investment in infrastructure and workforce investment have a significant impact in the dynamic of the system.
Sustainability
2019 - BARABÁS, CARLOS; LIMA, ANA C. de S.; SABUNDJIAN, GAIANE
Over the years, sustainability has been a major theme discussed by the leading environmental organizations around the world. Excessive consumption is one of the factors that is directly connected to environmental issues, interfering with the sustainability capacity of the Earth. Attitudes and behavior are influenced by both conscious (explicit) or unconscious (implicit) associations that subjects have in their memory. In order to identify unconscious associations, specific implicit memory tests are required, such as the Implicit Association Test (IAT), which is widely used to measure implicit associations towards several themes. This work aims to present the results from a pretest using the IAT to identify and measure the implicit associations of a group of environmental specialists regarding consumption and sustainability. By using the FreeIAT software, the IAT was customized for this research. The pretest with environmental specialists was conducted to check the consistency of the customized IAT. The Cronbach´s alpha was applied to measure the reliability of the test and showed good internal consistency. Since the results from the pretest with the specialists demonstrated that the customized IAT is reliable and consistent, this test can be applied to other groups of subjects to identify the implicit associations towards consumption and sustainability. The data obtained from the administration of the customized IAT will contribute to many research fields related to the environment, consumption, sustainability, energy and development.
Educação ambiental e sustentabilidade
2019 - ESCANHOELA, CORDELIA M.F.; SABUNDJIAN, GAIANE; LIMA, ANA C. de S.
Este trabalho apresenta um estudo sobre a implementação do reator inovador System - Integrated Modular Advanced Reactor (SMART) no Brasil. Desenvolvido pelo Korea Atomic Energy Research Institute (KAERI) e com potência elétrica de 100MWe, esse reator pode atender a uma demanda de cerca de 100.000 habitantes. A escolha deste reator nuclear inovador está alicerçada, primeiramente, na análise do cenário energético nacional, no qual é demonstrada tanto a necessidade da expansão energética no Brasil quanto na imprescindível escolha de fontes alternativas de energia de maneira a atender as exigências de sustentabilidade e atenuação dos impactos ambientais. Dentro do contexto de complementariedade da matriz energética nacional associada à descentralização da geração de energia elétrica; o projeto envolvendo um reator nuclear pequeno e modular do tipo Power Water Reactor (PWR) prova ser uma escolha assertiva inclusive do ponto de vista econômico, já comprovado por meio de métodos econômicofinanceiros e ainda, pelo aproveitamento da expertise existente no país.
Containment pressure analysis methodology during a LBLOCA with COCOSYS code
2018 - SILVA, DAYANE F.; LIMA, ANA C. de S.; SABUNDJIAN, GAIANE
During a nuclear power plant basic design accident, the containment integrity is a determining factor for the accident severity. The pressure and temperature conditions inside the containment in case of a Large Break Loss of Coolant Accident (LBLOCA) must be verified. This paper presents a containment pressure and temperature analysis methodology of a Brazilian PWR, Angra 2, using a code that simulates guillotine rupture - RELAP5 - and the COCOSYS code, which analyzes the containment pressure from the accident conditions. The Angra 2 containment behavior results during the design basis accidents studied - primary cooling system cold and hot legs guillotine ruptures - were satisfactory when compared to those presented in the Final Safety Analysis Report (FSAR / A2) and the pressure distributions were below the containment design pressure value (6.3bar).
A panoramic view of nuclear science and technology education worldwide
2018 - BARABAS, ROBERTA de C.; LIMA, ANA C. de S.; SABUNDJIAN, GAIANE
Nuclear energy has been used as a source of clean energy with many benefits. Nevertheless, it is still addressed with prejudice. The atomic bombing of Hiroshima and Nagasaki during World War II (1945), the Three Mile Island accident (1979), Chernobyl accident (1986), the crash of the cesium-137 in Goiânia, Brazil (1987), and the accident in Fukushima (2011) may have been responsible for the negative image of nuclear energy. Researches on education have been conducted with students concerning the conceptual and practical issues of nuclear energy. This work aims to review the literature about nuclear energy education around the world in both, elementary school and high school. Since most educational researches on nuclear energy were published after 1980, this literature review covered the researches that have been published since 1980. The data were presented in chronological order. The results from the literature review provided a clear visualization of the global nuclear energy educational scenario, showing that the theme is still addressed with prejudice due to an incorrect view of nuclear energy and a limited view of its benefits. Concerning the science textbooks, the literature reports that the theme should be better addressed, encouraging students to research more about it. The data from this literature review will serve as a reference for a future proposal for a teaching training program for Brazilian science/physics high school teachers using a new teaching approach.
Comparative study of methodologies for measuring corporate social responsibility
2018 - MUTARELLI, RITA de C.; LIMA, ANA C. de S.; SABUNDJIAN, GAIANE
The Corporate Social Responsibility (CSR) is a current issue increasingly present in the strategic planning of the companies. Although managers of public or private organizations have turned their attention to social and environmental issues in their strategic actions, measuring the social responsibility of a company is not an easy task. This paper aims to observe the eight most relevant methodologies of CSR measurement and establish a comparative analysis among them by considering the scope and feasibility of each methodology. The most relevant CSR methodologies were selected. The main characteristics of each of the eight tools were observed and compared. The results demonstrated that although most methodologies have strong measuring characteristics the Ethos Indicators consist of the most effective tool for measuring CSR mainly regarding the institutional issues
A neuroscience-based methodology to identify the implicit associations of brazilian science teachers towards nuclear technology
2018 - BARABAS, ROBERTA de C.; LIMA, ANA C. de S.; SABUNDJIAN, GAIANE
Science, technology, and innovation play an essential role in helping countries increase the quality of life they offer their citizens. Since the discovery of nuclear fission in the 30s, the peaceful applications of nuclear technology have benefited several fields. Improved crops, preservation of food, health, environment protection and a stable supply of energy can be cited as contributions of nuclear technology for global wellbeing. Despite all benefits that result from the peaceful uses of nuclear technology, it is still addressed with prejudice. Prejudices may be explicit (conscious) or implicit (unconscious). Either explicit or implicit, prejudices interfere with individuals’ attitudes. This paper aims to assess the implicit associations of Brazilian science teachers towards nuclear technology by administering the Implicit Association Test (IAT). Identifying their implicit associations will contribute for the understanding of prejudices that may interfere with their teaching. A pretest with nuclear specialists was administered to check the consistency of the IAT. Subsequently, it was administered to the science teachers. The results of the IAT demonstrated more positive associations towards oil. The next step consists of proposing a methodology to change implicit associations of Brazilian science teachers towards nuclear technology.
Containment pressure analysis methodology during a LBLOCA with iteration between RELAP5 and COCOSYS
2017 - SILVA, DAYANE F.; SABUNDJIAN, GAIANE; LIMA, ANA CECILIA S.
Study of the economic viability of the innovative nuclear reactor SMART in Brazil
2017 - ESCANHOELA, CORDELIA M.F.; LIMA, ANA C. de S.; SABUNDJIAN, GAIANE
The main objective of this study is to evaluate the economic viability of the installation and operation of the innovative System - Integrated Modular Advanced Reactor (SMART) in Brazil. SMART, developed by the Korea Atomic Energy Research Institute (KAERI), is a small and modular Power Water Reactor (PWR), presents electric power of 100 MW and thermal power of 330 MW; it has a passive safety system and integral refrigeration configuration, characteristics that, allied with modularization, simplification and technological improvements, give SMART greater reliability and economy when compared to conventional reactors. SMART presents, in addition to electricity production, the functions of seawater desalination and district heat generation. The research is based on projections of energy demand in the medium and long term with emphasis on electricity and search for the reduction of greenhouse gases. These previsions indicate the need for energy expansion and diversification of the current sources in Brazil, predominantly water sources. The methodology used is based on the cost of electric generation, production capacity and construction time of SMART, adopting the investment model similar to the Angra 3 plant and the use of mirrored costs between the plants. The feasibility of the project was evaluated through the financial criteria: Internal Rate of Return (IRR), Net Present Value (NPV) and Weighted Average Cost of Capital (WACC), whose revenue should be generated through a tariff passed on to the consumer.
Heat transfer mode in the core of the Angra 2 nuclear power plant during small break loca obtained with RELAP5 code
2013 - SABUNDJIAN, GAIANE; BELCHIOR JUNIOR, ANTONIO; CONTI, THADEU das N.; ROCHA, MARCELO da S.; ANDRADE, DELVONEI A. de; TORRES, WALMIR M.; MACEDO, LUIZ A.; UMBEHAUN, PEDRO E.; MESQUITA, ROBERTO N. de; LIMA, ANA C. de S.
This work aims to identify the heat transfer mode with RELAP5/MOD3.2.gama code in the core of Angra 2 facility. The postulate accident is the Loss of Coolant Accident (LOCA) in the primary circuit for Small Break (SB), which is described in Chapter 15 of the Final Safety Analysis Report of Angra 2 (FSAR). The accident consists basically of the total break of the cold leg of Angra 2 facility. The rupture area considered was 380 cm2, which represents 100% of the primary circuit pipe °ow area. The Emergency Core Cooling System (ECCS) e±ciency is also tested in this accident. In this simulation, failure and repair criteria are adopted for the ECCS components in order to verify the system operation e±ciency - preserving the integrity of the reactor core and guaranteeing its cooling - as expected by the project design. SBLOCA accidents are characterized by a fast blowdown in the primary circuit to values that activate the low pressure injection system followed by the water injection from the accumulators. The thermal-hydraulic processes inherent to the accident phenomenon, such as hot leg vaporization and consequently core vaporization cause inappropriate °ow distribution in the reactor core that can lead to reduction in the core liquid level, up to the point that the ECCS is able to re°ood it. This work shows the mode numbers and the wall convection heat transfer used in the RELAP5 code that were accessed during the execution of the program. The results showed that the numerical simulations with RELAP5 were satisfactory and that the ECCS worked e±ciently, guaranteeing the integrity of the reactor core.