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Simulação do reator TRIGA IPR-R1 utilizando metodos de transporte por Monte Carlo / TRIGA IPR-R1 reactor simulation using Monte Carlo transport methodsDalle, Hugo Moura 29 July 2005 (has links)
Orientador: Elias Basile Tambourgi / Tese (doutorado) - Universidade Estadual de Campinas, Faculdade de Engenharia Quimica / Made available in DSpace on 2018-08-04T19:28:53Z (GMT). No. of bitstreams: 1
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Previous issue date: 2005 / Resumo: A utilização do método Monte Carlo na simulação do transporte de partículas em reatores nucleares é crescente e constitui uma tendência mundial. O maior inconveniente dessa técnica, a grande exigência de capacidade de processamento, vem sendo superado pelo contínuo desenvolvimento de processadores cada vez mais rápidos. Esse contexto permitiu o desenvolvimento de metodologias de cálculo neutrônico de reatores nas quais se acopla a parte do transporte de partículas, feita com um código de Monte Carlo, ao cálculo de queima e decaimento radioativo. Neste trabalho tal metodologia de simulação é implantada, validada para reatores de pesquisas, notadamente os do tipo TRIGA e finalmente utilizada na simulação neutrônica do reator TRIGA IPR ¿ RI do CDTN/CNEN. O sistema de códigos empregados é constituído pelos amplamente utilizados códigos MCNP4B (transporte por método Monte Carlo) e ORIGEN2.1 (queima e decaimento radioativo). Apesar dos esforços recentes no sentido de agrupar as duas etapas de cálculo, transporte e queima, em um único código, até o momento esta opção não está disponível e, portanto, um terceiro código é utilizado para realizar o acoplamento transporte/queima. Neste trabalho utilizou-se para tal o código MONTEBURNS. O sistema formado por estes três códigos permitiu obter os parâmetros neutrônicos de interesse do IPR ¿ R1 através apenas de simulação teórica, sem a necessidade de qualquer tipo de ajuste baseado em dados experimentais, em boa concordância com os valores medidos... Observação: O resumo, na íntegra, poderá ser visualizado no texto completo da tese digital / Abstract: The use of Monte Carlo methods in particles transport simulations of nuclear reactor is growing fast and constitutes a strong tendency all over the world. The major inconvenient of such techniques is the huge demand of processing power which has been surpassed the development of reactor physics calculation methodologies in which the particles transport part, made by a Monte Carlo transport code, is linked with the burnup and radioactive decay part of the simulation. On this work a such simulation methodology is made operational, validated for research reactors, mainly for TRIGA reactor and finally utilized for reactor physics simulation of the CDTN¿s TRIGA IPR ¿ R1. The adopted codes system is constituted by the widespreadly used codes MCNP4B (Monte Carlo transport) and ORIGEN2.1 (burnup and radioactive decay). In spite of the very recent efforts toward get together both, transport and burnup, in only one code at the moment this is a not available option and therefore, a third code is needed to carry out the linkage transport/burnup. MONTEBURS code was used to this purpose. This three codes system has allowed to obtain the physical parameters of IPR ¿ R1 calculated using only theoretical simulation without any kind of experimental adjustment or interaction between experiments and calculation in good agreement with measured values... Note: The complete abstract is available with the full electronic digital thesis or dissertations / Doutorado / Sistemas de Processos Quimicos e Informatica / Doutor em Engenharia Química
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Desenvolvimento e aplicacao de modelo multidimensional para a avaliacao da qualidade educacional no programa de pos-graduacao stricto sensu do IPEN / Development and application of multidimensional model for the quality evaluation of graduate-level education in program of the IPENMIORANZA, CLAUDIO 09 October 2014 (has links)
Made available in DSpace on 2014-10-09T12:27:17Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T13:59:15Z (GMT). No. of bitstreams: 0 / As instituições de ensino superior têm se preocupado com a qualidade do produto que oferecem à sociedade e, com o objetivo de conseguir melhores resultados, precisam prestar serviços com alto grau de valor e de qualidade. O caráter inédito deste estudo foi o desenvolvimento de um Modelo Multidimensional para a Avaliação da Qualidade Educacional, denominado MULTQUALED. O modelo foi estruturado a partir de normas e de modelos da qualidade utilizados em outros setores econômicos onde foram criados quatro instrumentos de coleta de dados, contemplando as dimensões organização didático-pedagógica, recursos humanos e infraestrutura, com o objetivo de qualificar e de quantificar ações para a melhoria contínua do processo de gestão da qualidade educacional. A aplicação do modelo ocorreu no Instituto de Pesquisas Energéticas e Nucleares de São Paulo (IPEN-CNEN/SP), no Programa de Pós-Graduação Stricto Sensu em Tecnologia Nuclear. As informações obtidas a partir da aplicação do modelo MULTQUALED evidenciaram fragilidades e aspectos positivos que auxiliarão a tomada de decisões com ações estratégicas, contribuindo com a melhoria contínua da qualidade educacional do programa. / Tese (Doutoramento) / IPEN/T / Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP
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Instituto de Pesquisas Energéticas e Nucleares - (1956-2000). Um estudo de caso à luz da história da ciência, da tecnologia e da cultura brasileiraGORDON, ANA M.P.L. 09 October 2014 (has links)
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Estudo comparativo dos riscos a saude publica e dos impactos ambientais na geracao de eletricidade pelo uso da energia nuclear, hidroeletrica e termoeletrica a carvao mineralGUIMARAES, CUSTODIO A. 09 October 2014 (has links)
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Investigação experimental da distribuição de temperaturas no reator nuclear de pesquisa TRIGA IPR-R1Mesquita, Amir Zacarias 29 April 2005 (has links)
Orientador: Elias Basile Tambourgi / Tese (doutorado) - Universidade Estadual de Campinas, Faculdade de Engenharia Quimica / Made available in DSpace on 2018-08-04T05:25:21Z (GMT). No. of bitstreams: 1
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Previous issue date: 2005 / Resumo: O Reator Nuclear de Pesquisa TRIGA IPR-RI completou em novembro de 2004, 44 anos de operação. Inicialmente sua potência máxima era de 30 kW térmicos, posteriormente acrescentaram-se mais elementos combustíveis ao núcleo aumentando a potência para 100 kW, sendo esta a atual potência licenciada. Novos combustíveis foram acrescentados recentemente permitindo que a potência atinja níveis de 250 kW. O TRIGA IPR-RI é um reator de piscina com o núcleo refrigerado por circulação natural. Apesar dos vários trabalhos de pesquisa realizados nesta instalação, notadamente em ativação neutrônica, existe uma carência de dados termo-hidráulicos teóricos e experimentais sobre seu funcionamento. Sendo assim rea1izou-se-se uma série de testes experimentais dando enfoque a medidas de temperatura no centro do elemento combustível, no núcleo e no poço, com o reator operando em vários níveis de potência. As experiências aqui relatadas fazem parte da programação de pesquisas do CDTN/CNEN, que têm como objetivo comissionar o Reator TRIGA IPR-RI para a operação rotineira a 250 kW. Este trabalho descreve os estudos analíticos e experimentais realizados com o intuito de determinar a distribuição das temperaturas no reator. Desenvolveu-se uma metodologia para a calibração e monitoração da potência dissipada pelo núcleo, implantando assim novos canais de medida de potência por processo térmico. A condutividade térmica do elemento combustível e o coeficiente de transferência de calor de seu revestimento para o refrigerante foram avaliados experimentalmente. Foi proposta uma formulação para a determinação do valor da condu1ância na interface entre combustível e seu revestimento (gap). Os resultados experimentais foram comparados com valores teóricos encontrados na literatura. Como subsídio às experiências, desenvolveu-se um sistema e um programa de coleta e processamento de dados para o reator, capaz de acompanhar em tempo real e registrar seus - principais parâmetros operacionais. As experiências realizadas permitiram uma melhor compreensão do comportamento termofluidodinâmico do reator, ajudando no aperfeiçoamento de sua modelagem e contribuindo para a sua segurança operacional / Abstract: The TRIGA-IPR-R1 Research Nuclear Reactor has completed 44 years in operation in November 2004. Its initial nominal thermal power was 30 kW. In 1979 its power was increased to 100 kW by adding new fuel elements to the reactor. Recently some more fuel elements were added to the core increasing the power to 250 kW. The TRIGA-IPR-R1 is a pool type reactor with a natural circulation core cooling system. Although the large number of experiments had been carried out with this reactor, mainly on neutron activation analysis, there is not many data on its thermal-hydraulics processes, whether experimental or theoretical 80 a number of experiments were carried out with the measurement of the temperature inside the fuel element, in the reactor core and along the reactor pool. During these experiments the reactor was set in many different power levels. These experiments are part of the CDTN/CNEN research program, and have the main objective of commissioning the 1RIGA-IPR-Rl reactor for routine operation at 250 kW. This work presents the experimental and theoretical analyses to determine the temperature distribution in the reactor. A methodology for the calibration and monitoring the reactor thermal power was also developed. This methodology allowed adding others power measuring channels to 1he reactor by using thermal processes. The fuel thermal conductivity and the heat transfer coefficient from the cladding to the coolant were also experimentatly valued. It was also presented a correlation for the gap conductance between the fuel and the cladding. The experimental results were compared with theoretical calculations and with data obtained from technical literature. A data acquisition and processing system and a software were developed to help the investigation. This system allows on line monitoring and registration of the main reactor operational parameters. The experiments have given better comprehension of the reactor thermal-fluid - dynamics and helped to develop numerical models, contributing to operational safety improvements / Doutorado / Sistemas de Processos Quimicos e Informatica / Doutor em Engenharia Química
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Contribution à la maîtrise du changement organisationnel et de son impact sur la sûreté : le cas de la transition d’une installation nucléaire du fonctionnement vers le démantèlement / A contribution to the management of organisational change and of its impact on safety : studying the transition from functionning to the decommissioning of a nuclear power plantPelleterat de Borde, Melchior 09 December 2013 (has links)
Le travail de thèse cherche à dresser une passerelle entre la question du changement organisationnel et celle des risques, à travers l'étude d'une phase complexe du cycle de vie d'une installation nucléaire : le passage du fonctionnement au démantèlement. Ce dernier clôt une dynamique d'exploitation et en hérite les habitudes, les circuits de communication et de décision, mais s'accompagne d'un changement organisationnel conséquent que les acteurs doivent apprendre et intégrer. Il s'agit donc d'interroger la dynamique de transformation organisationnelle en la replaçant dans un mouvement plus global d'évolution d'une installation dans le temps. Nous cherchons à comprendre dans quelle mesure l'organisation mise en place répond ou non aux besoins de l'installation et de ses acteurs. La thèse montre que la transition s'inscrit dans une temporalité propre où les conséquences et la compréhension du changement ne sont pas homogènes. La transition s'accompagne d'une appropriation différée des nouveaux circuits de décision ainsi que d'une recomposition des réseaux d'acteurs. Cette recomposition met en évidence une tendance au contournement temporaire des structures légitimes de l'organisation qui permet la synthèse progressive des nouvelles contraintes et des anciens univers référentiels des acteurs. / The thesis seeks to establish a bridge between the issue of organizational change and safety, through the study of a complex phase of the life cycle of a nuclear facility: the transition from operation to decommissioning. Decommissioning closes an operating dynamics and inherits habits, communication channels and decision, but is accompanied by an organizational change plant operatives must understand and take possession of. The thesis therefore examines the dynamics of organizational transformation by taking into account a broader movement of evolution of a system over time. We seek to understand how the organization does or does not meet the needs of the facility and its actors. We show that the transition follows in its own temporality and that the consequences and their understanding are not homogeneous. The transition is accompanied by a deferred appropriation by the plant operatives of the new decision circuits, and a radical recomposition of operatives networks. This reconstruction reveals a trend towards a temporary bypass of legitimate organizational structures, as well as a gradual synthesis of the old and new referential universes for the plant operators.
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Anti-nuclear Movements in Discursive and Political Contexts : Between Expert Voices and Local ProtestsTarasova, Ekaterina January 2017 (has links)
Energy policies which maintain and extend nuclear energy are often opposed by anti-nuclear movements. Ambitious plans for developing nuclear energy in Russia, constructing a first nuclear plant in Poland, and lifting the ban on nuclear energy while allowing the replacement of old reactors in Sweden are examples of such energy policies. In contrast to the massive anti-nuclear movements of 1970-1990s, recent anti-nuclear movements are not organized as national protest campaigns. This thesis examines repertoires of anti-nuclear movements in the alleged “Nuclear Renaissance” period. Repertoires of anti-nuclear actions are analyzed from the perspective of discursive and political opportunities of anti-nuclear movements. Discursive opportunities are enabled or hindered in the ordering of nuclear energy discourses, making messages and actions of social movements legitimate or illegitimate. While discourses of anti-nuclear movements are complex, official discourses of nuclear energy featuring arguments about profitability, energy security and environmental security in connection to nuclear energy development, resonate more with broader socio-political developments. Ordering of discourses is established in such a way that expert rhetoric becomes a standard approach for discussing nuclear energy, while references to emotions and subjective matters are unacceptable. Political contexts of anti-nuclear movements provide opportunities for environmental NGOs, one kind of actor in anti-nuclear movements, to pursue nonconfrontational strategies and engage in institutional channels, where they can contribute their expert knowledge. Concurrently, another actor in anti-nuclear movements, local anti-nuclear groups, on the one hand, share argumentative structures with environmental NGOs, and, on the other hand, attempt to mobilize local population and organize local protests. Due to limited opportunities for attention from the national media and focus on local issues, local protests are not featured in the national media, which is crucial for national protest actions. The differences in repertoires between these two kinds of actors and absence of actors opting for mass engagement provide insight into repertoires of anti-nuclear movements as a whole. This thesis demonstrates how discursive opportunities of social movements, which result from competing discourses of movements and their counter-agents, and political opportunities structure repertoires of actions of these movements. / Energipolitik som upprätthåller och utökar användandet av kärnkraft motarbetas ofta av antikärnkraftsrörelser. Exempel på sådan energipolitik är de ambitiösa planerna på att utveckla kärnkraft i Ryssland, att bygga ett första kärnkraftverk i Polen, och att häva förbudet mot kärnkraft samt möjliggöra utbyte av gamla reaktorer i Sverige. I motsats till de massiva antikärnkraftsrörelserna under 1970-1990, är de nya rörelserna inte organiserade som nationella protestkampanjer. Denna avhandling undersöker vilka olika handlingssätt antikärnkraftsrörelserna i den påstådda "Nuclear Renaissance"-perioden använder. Antikärnkraftsrörelsernas olika sätt att agera analyseras ur diskursiva och politiska möjligheter. Diskurser av antikärnkraftsrörelser är komplexa, när officiella diskurser om kärnkraft möter argument om lönsamhet, energisäkerhet och miljösäkerhet i samband med kärnkraft utveckling, anknyter den mer till en bredare socio-politiska utveckling. Diskurser etableras på ett sådant sätt att expertretorik blir en standardiserad metod för att diskutera kärnkraft, medan hänvisningar till känslor och subjektiva frågor är oacceptabla. Det politiska sammanhanget ger möjligheter till miljöorganisationer, en typ av aktör inom antikärnkraftsrörelsen, att bedriva nonconfrontational strategier och engagera sig via institutionella kanaler, där de kan bidra med sin sakkunskap. Samtidigt som en annan aktör, lokal antikärnkraftsgrupper, å ena sidan dela argument med miljöorganisationer, men å andra sidan försök att mobilisera lokalbefolkningen och anordna lokala protester. Eftersom lokala protester inte visas i nationella medier får de begränsade möjligheter till medial uppmärksamhet, något som är avgörande för nationella protestaktioner. Skillnaderna i sätt att agera mellan dessa två typer av aktörer och frånvaro av aktörer som väljer massengagemang ger insikt i de olika handlingssätt som används av antikärnkraftsrörelser som helhet.
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Impacts of primary energy constraints in the 21st centuryNel, Willem P. 25 March 2010 (has links)
D.Phil. / Global society has evolved into a complex multi-dimensional system in which it has become increasingly difficult to construct and maintain a systemic model of cause and effect. Specialisation and abstraction in the various disciplines of scientific and societal complexity has led to divergent theories of sustainability. Failure to integrate real life problems across disciplines poses a threat to modern society because the causal links between disciplines are unattended in many instances and events in one dimension could lead to catastrophic unintended consequences in another. In light of the above, this thesis contributes towards the multi-disciplinary integration of some of the most important sustainability concerns of modern society, namely Energy Security, Economic Growth and Global Warming. Analysing these real-life sustainability issues in a multi-disciplinary context leads to conclusions that are controversial in terms of established philosophical worldviews and policy trends. Firstly, the thesis establishes deterministic expectations of an imminent era of declining Energy Security resulting from the exhaustion of non-renewable fossil fuel resources, despite optimistic expectations of technology improvements in alternative energy sources such as renewable and nuclear. Secondly, the exhaustion of non-renewable fossil fuel resources imposes limits to the potential sources of anthropogenic carbon emissions that render the more pessimistic emissions cases considered in the global warming debate irrelevant. The lower level of attainable carbon emissions challenges the merits of the conventional carbon feedback cycle with the result that the predicted global warming is within acceptance limits of the contemporary global warming debate. Thirdly, the consequences of declining Energy Security on socio-economic welfare is a severe divergence from historical trends and demands the reassertion of the role of energy in human development, including Economic Growth theory. The thesis develops a novel economic growth model that treats energy as an explicit and Autonomous Factor of Production, thereby facilitating plausible predictions of future Economic Growth potential. The results challenge the sustainability of the current free-market capitalist economic system and demand strong policy responses to avoid the collapse of modern society.
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Nuclear narratives in UK energy policy, 1955-2008 : exploring the dynamics of policy framingRough, Elizabeth Kate January 2012 (has links)
No description available.
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Jaderná energetika a její budoucnost / Nuclear energy and its futureEretová, Kamila January 2009 (has links)
This work deals with the potential of nuclear energy in general and in our country. Nuclear energy offers as almost a necessary alternative to fill growing demand for electricity in our country and the world. Increased attention is paid to the electricity market in our country, the role of nuclear energy in the Czech energy mix and the possibilities of its use in the future as an alternative to other energy sources (renewable, fossil resources), and savings and imports from abroad. The author summarizes the main benefits, but also the risk that nuclear energy brings. Does not forget the attitude of environmentalists, opponents and the public to the nuclear issue, which improves long-term, giving scope for the use of nuclear energy.
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