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核能科技的新聞建構-以福島核災報導為例 / The news construction of nuclear technology – take the Fukushima nuclear disaster reports as an example陳雅妤, Chen, Ya Yu Unknown Date (has links)
本研究以福島核災期間的新聞報導為分析對象,透過兩階段的新聞內容分析,比較福島核災發生當月以及週年前夕的新聞報導。研究發現越接近福島核災週年,媒體關注越高;福島核災後一個月內的新聞以因應框架為主,一年後的主要框架則轉為衝突及人情趣味框架;福島核災週年的報導戲劇化程度較一年以前為高,而兩階段共同的缺點則為消息來源過於單一化。本研究檢視福島核災報導的優點及未盡之處,以提供實務上諸多參考。 / This thesis attempts to analyze the news reports of Fukushima Nuclear Disaster. By comparing the news coverage between March 11 and April 10 2011, and February 12 and March 11 2012, we found when the anniversary of the Fukushima Nuclear Disaster approaching, the amount of news reports gradually increased. The dominant frame of the first stage of this study is the strategy frame, and the second stage are the conflict frame and the human interest frame. This study also found the amount of the dramatic style of coverage in the second stage is higher than that in the first stage. And the shortcoming of both the two stage is the lack of diversity of the sources.
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An autonomous long-term fast reactor system and the principal design limitations of the conceptTsvetkova, Galina Valeryevna 30 September 2004 (has links)
The objectives of this dissertation were to find a principal domain of promising and technologically feasible reactor physics characteristics for a multi-purpose, modular-sized, lead-cooled, fast neutron spectrum reactor fueled with an advanced uranium-transuranic-nitride fuel and to determine the principal limitations for the design of an autonomous long-term multi-purpose fast reactor (ALM-FR) within the principal reactor physics characteristic domain. The objectives were accomplished by producing a conceptual design for an ALM-FR and by analysis of the potential ALM-FR performance characteristics. The ALM-FR design developed in this dissertation is based on the concept of a secure transportable autonomous reactor for hydrogen production (STAR-H2) and represents further refinement of the STAR-H2 concept towards an economical, proliferation-resistant, sustainable, multi-purpose nuclear energy system. The development of the ALM-FR design has been performed considering this reactor within the frame of the concept of a self-consistent nuclear energy system (SCNES) that satisfies virtually all of the requirements for future nuclear energy systems: efficient energy production, safety, self-feeding, non-proliferation, and radionuclide burning. The analysis takes into consideration a wide range of reactor design aspects including selection of technologically feasible fuels and structural materials, core configuration optimization, dynamics and safety of long-term operation on one fuel loading, and nuclear material non-proliferation. Plutonium and higher actinides are considered as essential components of an advanced fuel that maintains long-term operation. Flexibility of the ALM-FR with respect to fuel compositions is demonstrated acknowledging the principal limitations of the long-term burning of plutonium and higher actinides. To ensure consistency and accuracy, the modeling has been performed using state-of-the-art computer codes developed at Argonne National Laboratory. As a result of the computational analysis performed in this work, the ALM-FR design provides for the possibility of continuous operation during about 40 years on one fuel loading containing mixture of depleted uranium with plutonium and higher actinides. All reactor physics characteristics of the ALM-FR are kept within technological limits ensuring safety of ultra-long autonomous operation. The results obtained provide for identification of physical features of the ALM-FR that significantly influence flexibility of the design and its applications. The special emphasis is given to existing limitations on the utilization of higher actinides as a fuel component.
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Analise socio-tecnica de processos de produção de tecnologias intensivas em conhecimento em paises subdesenvolvidos : a trajetoria de uma empresa nuclear e espacial argentina (1970-2005) / Sociotechnical analysis of knowledge-intensive technologies production processes in underdeveloped countries: the case of an Argentinean nuclear and space company (1970-2005)Versino, Mariana Selva 28 August 2006 (has links)
Orientador: Hernan Eduardo Thomas / Tese (doutorado) - Universidade Estadual de Campinas, Instituto de Geociencias / Made available in DSpace on 2018-08-07T09:01:36Z (GMT). No. of bitstreams: 1
Versino_MarianaSelva_D.pdf: 1141722 bytes, checksum: 48efd0a98f87631b89b1e0c3fa9989f4 (MD5)
Previous issue date: 2006 / Resumo: A tese analisa como tem sido possível o desenvolvimento de tecnologias intensivas em conhecimento bem sucedidas em termos comerciais, em países em que existe escassa relação entre pesquisa e produção e onde o usual é a manufatura de bens com pequeno valor agregado. O estudo focaliza-se em processos concretos de criação e incorporação de conhecimentos à produção, desde uma abordagem sócio-técnica que integra as dimensões sociais, econômica, política e ideológica, analisadas de forma isolada e como ¿fatores externos¿ à produção da tecnologia na literatura existente. A pesquisa analisa as estratégias desenvolvidas pelos diferentes atores (engenheiros, pesquisadores, técnicos, empresários, clientes, fornecedores, funcionários etc.) participantes dos processos de construção de tecnologias intensivas em conhecimentos.Para isso, se estuda a trajetória sócio-técnica de uma empresa Argentina de capital nacional, exportadora de tecnologia nos setores espacial e nuclear, com uma permanência no mercado há mais de uma descada, e que baseia sua vantagem competitiva no uso intensivo do conhecimento. Utilizam-se categorias teóricas da sociologia da tecnologia e da economia da inovação, a partir de uma triangulação conceitual e de uma análise crítica para a compreensão da realidade latino-americana. A metodologia do trabalho é qualitativa e histórica. Utiliza fontes secundárias além da realização de trabalho de campo com entrevistas na empresa. A tese leva a compreender os processos de aprendizagem, produção e utilização do conhecimento em países subdesenvolvidos e ao enriquecimento das ferramentas teórico-conceituais do campo Ciência, Tecnologia e Sociedade (CTS) para a análise dos processos de mudança tecnológica e inovação na América Latina. Ao mesmo tempo, os resultados da pesquisa são um insumo de interesse para o desenho e planejamento das políticas de C&T e de inovação nacionais e regionais / Abstract: The thesis analyzes how has been possible the development of knowledge-intensive technologies comercially suscessful, in countries where there is a weak relationship between research and production and where the usual is the manufacture of goods with small joined value. The study is focused in concrete processes of criation and incorporation of knowledge to production, from a sociotechnical approach that integrates the social, economical, political and ideological dimensions considered in an isolated way and as ¿external factors¿ to the production of technology in the existent literature. The research seeks to understand the strategies developed by the different actors (engineers, researchers, technicians, entrepreneurs, customers, suppliers, employees etc.) participants of the processes of construction of knowledge-intensive technologies. For that, it is studied the sociotechnical trajectory of an Argentinean company of national capital, technology exporter in the space and nuclear sectors, with a permanence in the market of more than one decade and that bases its competitive advantage on the intensive use of knowledge. Theoretical categories of the sociology of technology and the economy of innovation are used, based on a conceptual triangulation and on a critical analysis for the understanding of the Latin-American reality. The methodology of the work is qualitative and historical. It uses secondary sources besides the accomplishment of field work with interviews in the company. The thesis intends to understand the learning processes, production and use of knowledge in underdeveloped countries and contribute to the enrichment of the theoretical tools of Science and Technology Studies (STS) for the analysis of the processes of technological change and innovation in Latin America. At the same time, the results of the research are an interesting input for the drawing and planning of Science, Technology and Innovation national policies / Doutorado / Doutor em Política Científica e Tecnológica
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Tecnologia nuclear e aplicações : ressignificações dos conceitos com o uso de material potencialmente significativo para estudantes do ensino médioSantos, Magda Dias de Oliveira 08 1900 (has links)
The proposal of this work was to make educational product that approach the theme of Nuclear Technology and its Applications in the context of School Education, within a holistic vision, providing the development of a pedagogical proposal that enables the didactic transposition of scientific knowledge. In this perspective, the use of Information and Communication Technologies (ICTs) were used, such as Hypermedia, a resource that allowed the interaction with various information related to the subject, starting from the pre-existing knowledge, with the purpose of observing the social representations About Nuclear Technology and its applications. It was intended to stimulate a reflection and search for solutions favorable to an environmentally sustainable future, awakening this student to the teaching of sciences, allowing their scientific literacy. Initially an investigation was done about the Nuclear Technologies means, through debates, addressing all the positive and negative points, reading texts, using videos and presenting dialogues on the subject. This interaction and this diagnosis, according to the Ausubel theory, allowed the student to construct his own knowledge, establishing connections of the everyday situations with the scientific knowledge addressed in the classroom. Also, the content was presented through scientific articles, simulations and applets, showing its origin and applicability through play material providing greater motivation to learn the concepts of nuclear energy and its technologies, as well as its importance for the socioeconomic and environmental development of a country. Problems were presented in order to stimulate the re-signification of concepts, followed by a verification of learning. From the work developed, a notebook was prepared with the pedagogical proposal, containing suggestions of texts, simulators, instructional videos, didactic activities, constituting a potentially significant material that could be used in the scientific literacy of students of basic education, especially for to stimulate the didactic transposition of nuclear and special knowledge and its applications. / A proposta deste trabalho foi elaborar um produto educacional com abordagem à temática da Tecnologia Nuclear e suas Aplicações no contexto da Educação Escolar, dentro de uma visão holística, proporcionando o desenvolvimento de uma proposta pedagógica que viabilize a transposição didática do conhecimento científico. Dentro desta perspectiva, foi feito o uso recursos das Tecnologias da Informação e Comunicação (TIC’s), tais como Hipermídias, recurso que permitiu a interação com diversas informações relacionadas com a temática, partindo dos conhecimentos pré-existentes, com intuito de observar as representações sociais de alunos da segunda série do ensino médio, a respeito da Tecnologia Nuclear e suas aplicações. Estimulou uma reflexão e buscaram-se soluções favoráveis para um futuro ambientalmente sustentável, despertando o interesse para o ensino de ciências, permitindo a sua alfabetização científica. Inicialmente foi feita uma investigação sobre o que se entende por Tecnologias Nucleares, através de debates, abordando pontos positivos e negativos, leitura de textos, uso de vídeos e apresentações dialogadas sobre o tema. Essa interação e esse diagnóstico, segundo a teoria de Ausubel da aprendizagem significativa, possibilitou ao aluno construir seu próprio conhecimento, estabelecendo conexões das situações do cotidiano com o conhecimento científico abordado em sala de aula. Também, foi apresentado o conteúdo através artigos científicos e simulações, mostrando sua origem e aplicabilidade através de material lúdico proporcionando maior motivação em aprender os conceitos relativos à energia nuclear e suas tecnologias, bem como sua importância para o desenvolvimento socioeconômico e ambiental de um país. Foram apresentadas situações problemas, de maneira a estimular as ressignificações de conceitos, e seguindo de uma verificação da aprendizagem. A partir do trabalho desenvolvido, foi elaborado um caderno com a proposta pedagógica, contendo sugestões de textos, simuladores, vídeo instrucional, atividades didáticas, representando um material potencialmente significativo, que pôde ser utilizado na alfabetização científica de estudantes da educação básica, para estimular a transposição didática de saberes da área nuclear e suas aplicações. / São Cristóvão, SE
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Development of a dynamic stochastic neutronic code for the analysis of conventional and hybrid nuclear reactors / Développement d’un code neutronique stochastique dynamique pour l’analyse de réacteurs nucléaires conventionnels et hybridesXenofontos, Thalia 19 January 2018 (has links)
La nécessité de simulations précises d’un réacteur nucléaire et spécialement dans des cas de cœurs et de configurations de combustible complexes, a imposé un usage accru de Codes Neutroniques Stochastiques (CNS). De plus, une demande a émergé pour des CNS à capacité inhérente d’estimation en continu de la variation de la composition isotopique du cœur ainsi qu’à couplage thermo-hydraulique optimisé. Des capacités supplémentaires sont exigées pour ces codes au vu de leur utilisation pour l’étude de nouveaux concepts de réacteur comme les Réacteurs Conduits par Accélérateur (RCA). Plus précisément, le réacteur hybride comprenant un réacteur nucléaire conventionnel et un accélérateur, nécessite l’analyse des deux composantes (réacteur – accélérateur) par un outil capable de couvrir le spectre énergétique neutronique extrêmement étendu qui caractérise ce système hybride.Ce travail présente les principales caractéristiques et capacités du nouveau CNS ANET (Advanced Neutronics with Evolution and Thermal hydraulic feedback) développé en collaboration du NCSR Demokritos (Grèce) avec CNRS/IDRIS et UPMC (France) et couvrant autant que possible les exigences exposées ci-dessus. ANET est basé sur la version ouverte du code PHE GEANT3.21 et est destiné à effectuer des analyses de cœurs de réacteurs conventionnels de génération II et III ainsi que des RCA. ANET est construit avec la capacité inhérentea) d’effectuer des calculs d’évolution du combustibleb) de simuler le processus de spallation dans le cas des RCAtout en tenant compte de la thermo-hydraulique du système.La version actuelle d’ANET utilise les trois estimateurs standard Monte Carlo pour le calcul du facteur de multiplication neutronique effectif (keff), soit l’estimateur de collision, celui d’absorption et celui de longueur de trace. Pour ce qui est du calcul du débit de fluence neutronique et des taux de réaction, les estimateurs de collision et de longueur de trace sont implémentés dans ANET suivant la procédure standard Monte Carlo. Pour ce qui concerne les calculs d’évolution (par exemple la consommation du combustible), une approche purement stochastique est implémentée dans ANET. A noter que la procédure usuelle consiste à coupler le code neutronique stochastique avec un code déterministe qui calcule la consommation du combustible. Pour les besoins d’analyse des RCA, le module INCL/ABLA a été incorporé dans ANET de façon à ce que le processus de spallation soit simulé par le code. La capacité d’ANET de simuler des configurations classiques a été démontrée en utilisant des résultats de mesures et des simulations de vérification effectuées en utilisant d’autres codes bien établis, ainsi qu’il est montré par la suite.Des données provenant de plusieurs installations et des analyses de problèmes-type internationaux ont été utilisés pour vérifier et valider les capacités d’ANET.Pour conclure, les résultats obtenus lors des comparaisons avec des mesures ou avec des simulations effectuées en utilisant d’autres codes neutroniques stochastiques ou déterministes, montrent qu’ANET possède la capacité de calculer correctement d’importants paramètres de systèmes critiques ou sous-critiques. Par ailleurs, l’application préliminaire d’ANET à des problèmes dépendant du temps fournit des résultats encourageants. ANET produit des estimations de consommation de combustible raisonnables, compte tenu que des incertitudes dans ce domaine sont souvent de l’ordre de 20% ou plus. Finalement, les performances du code dans le cas de KUCA montrent qu’ANET peut analyser des RCA de façon satisfaisante. / The necessity for precise simulations of a nuclear reactor especially in case of complex core and fuel configurations has imposed the increasing use of Monte Carlo (MC) neutronics codes. Besides, a demand of additional stochastic codes’ inherent capabilities has emerged regarding mainly the simulation of the temporal variations in the core isotopic composition as well as the incorporation of the T-H feedback. In addition to the above, the design of innovative nuclear reactor concepts, such as the Accelerator Driven System (ADSs), imposed extra requirements of simulation capabilities. More specifically, the combination of an accelerator and a nuclear reactor in the ADS requires the simulation of both subsystems for an integrated system analysis. Therefore a need arises for more advanced simulation tools, able to cover the broad neutrons energy spectrum involved in these systems.This work presents the main features and capabilities of the new MC neutronics code ANET (Advanced Neutronics with Evolution and Thermal hydraulic feedback), being developed in NCSR Demokritos (Greece) in cooperation with CNRS/IDRIS and UPMC (France) and intending to meet as effectively as possible the above described modelling requirements. ANET is based on the open-source version of the HEP code GEANT3.21 and is targeting to the creation of an enhanced computational tool in the field of reactor analysis, capable of simulating both GEN II/III reactors and ADSs. ANET is structured with inherent capability of (a) performing burnup calculations and (b) simulating the spallation process in the ADS analysis, while taking T-H feedback into account.The current ANET version utilizes the three standard Monte Carlo estimators for the neutron multiplication factor (keff) calculation, i.e. the collision estimator, the absorption estimator and the track-length estimator. Regarding the simulation of neutron fluence and reaction rates, the collision and the track-length estimators are implemented in ANET following the standard Monte Carlo procedure. For the burnup calculations ANET attempts to apply a pure Monte Carlo approach, adopting the typical procedure followed in stochastic codes. With respect to code improvements for the ADS analysis, so far ANET has incorporated the INCL/ABLA code so that the spallation process can be inherently simulated. The ANET reliability in typical computations was tested using observational data and parallel simulations by different codes as described in the following chapters.Various installations and international benchmarks were considered suitable for the verification and validation of all the previously mentioned features incorporated in the new code ANET. The obtained results are compared with experimental data from the nuclear infrastructures and with computations performed by well-established stochastic or deterministic neutronics codes and show satisfactory agreement with both measurements and independent computations, verifying thus ANET’s ability to successfully simulate important parameters of critical and subcritical systems. Also, the preliminary ANET application for dynamic analysis is encouraging since it indicates the code capability to inherently provide a reasonable prediction for the core inventory evolution taking into account the uncertainties of the order of 20% and even higher that are traditionally expected in core inventory evolution calculations. Lastly, the code performance in the KUCA case was found satisfactory demonstrating thus inherent capability of analyzing ADSs.
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Zauberstab der AtomwissenschaftAbele, Johannes 17 April 2014 (has links) (PDF)
No description available.
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Zauberstab der Atomwissenschaft: Hans Geiger und die Magie der KerntechnikAbele, Johannes January 2001 (has links)
No description available.
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Fotografie und atomare Katastrophe / die visuelle Repräsentation der Ereignisse von Hiroshima / Nagasaki und TschernobylBürkner, Daniel 05 May 2015 (has links)
Die Dissertation setzt sich mit den fotografischen Repräsentationen der Atombombenabwürfe auf Hiroshima und Nagasaki sowie der Havarie des Kernkraftwerks Tschernobyl auseinander. Dabei werden künstlerische, dokumentarische und touristische Bilder analysiert, die sich der jeweiligen Strahlenkatastrophe oftmals erst Jahre nach dem Ereignis annehmen und ikonografische oder medial-materielle Bezüge zu ihr aufweisen. Es zeigen sich zentrale Strategien, atomare Katastrophen, seien sie militärischer oder ziviler Natur, in fotografische Bilder überzuführen. Gerade das eigentliche Unvermögen, die visuell nicht sichtbaren Strahlenemissionen oder die Komplexität der Vorgänge auf atomarer Ebene zu visualisieren, hat sich als prägend erwiesen und bestimmt als Paradigma der Unsichtbarkeit die kulturelle Rezeption der Ereignisse. Es ist dieser Umgang mit den Abstraktionspotentialen der nuklearen Technologie, die im aktuellen Spannungsfeld ökologischer, sozialer und energietechnologischer Bildpolitik ihre Relevanz stets von neuem unter Beweis stellt. / The dissertation project seeks to analyse the photographic positions that deal with the atomic bomb attacks on Hiroshima and Nagasaki and the accident of the nuclear power plant in Chernobyl. This focus includes press photographs of the events as well as artistic, documentary and touristic images that take an approach towards the disasters often years after and hereby form iconographic or material references to the events. The study reveals central strategies for photographic images of atomic catastrophes, be they of military or civil nature. It is the inability to visualize non-visible nuclear rays or the complexity of processes on an atomic level that has turned out to be crucial. This incapacity of making images, a paradigm of invisibility, substantially coins the cultural role of the events. The question of how a society deals with these abstract potentials of nuclear technology has turned out to be always anew of high relevance in regard to ecological, social and technological policies of images.
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