近年來，在全球氣候變遷與化石燃料價格高漲的影響之下，節能減碳成了各國政府能源政策的圭臬。正因如此，核能重新被視為一種可行的替代能源，獲得長足的發展。但這股核能復興潮並沒有持續太久，2011年日本福島核事故的發生，使全球核能產業陷入了新一波的低潮。這場核能浩劫，與25年前在前蘇聯發生的車諾比核事故如出一轍，都影響了許多國家在核能政策上的選擇。 本研究針對俄羅斯核能產業之發展進行探討，以了解其核能利用上的立場及發展策略。特別是在2011年日本福島核災後，俄羅斯在核能政策上是否有所轉變。值得注意的是，俄羅斯國家原子能公司(Rosatom)，作為國營之核能企業，展現了其企圖心，矢言成為新一代的全球核能復興先驅。 本研究認為，俄羅斯仍不會放棄核能的利用，而且也將持續進行核能復興的政策路線，尋求擴大在全球核電市場上的影響力。核能對俄羅斯而言，除了經濟方面的利益外，同時也兼具了政治、能源安全上的意涵。除非未來科技進步，足以發展出一種高效率同時兼顧生態發展的發電方式，否則近期內俄羅斯的核能發展現狀將不會有太大的改變。 / In recent years, under the influence of global climate change and high fossil fuel prices, carbon reduction has become a model as energy policy for many governments. Because of that, nuclear energy was re-considered a viable alternative energy source, and developed rapidly. But this trend of "nuclear renaissance" did not last too long, due to Fukushima nuclear accident in Japan in 2011, the global nuclear industry fell into another serious decline. Just like Chernobyl nuclear accident that occurred 25 years ago in former Soviet Union, This nuclear catastrophe have affected many countries in nuclear energy policies. In this study, we discussed the development of Russia's nuclear industry in order to understand its position on nuclear energy and development strategies. Particularly, we would like to see if there is a significant change in Russia's nuclear energy policy after Fukushima nuclear disaster in 2011. It is noteworthy that the State Atomic Energy Corporation Rosatom, as a state-owned nuclear company, demonstrated its ambition, and vowed to be a pioneer of global nuclear renaissance in a whole new era. In this study, we concluded that Russia will not give up nuclear energy, but also continue its nuclear renaissance energy policy routes, seeking to expand influence in the global nuclear power market. In addition to economic benefits, for Russia, nuclear energy also means both the political and energy security implications. Unless the technological progress in the future that is enough to develop a high-efficiency and ecological way of power generation, otherwise, Russia's nuclear energy development situation will not have a significant change in the near term.

伊朗伊斯蘭共和國為中東地區主要國家之一。自1957年與美國合作發展核能以來，除了在柯梅尼政權初期曾短暫中斷外，歷任的領導人皆大力支持核科技的發展。從近年來的發現，顯示伊朗正在持續進行某些秘密的核計畫，使得國際憂心伊朗可能有發展核武的意圖。一旦伊朗擁有核武，將對國際安全產生重大衝擊。 本文分析的重點，在於伊朗發展核科技的背景、動機、經過，還有各國對伊朗核計畫的態度，以及伊朗核武化之後對國際安全的衝擊。 / The Islamic Republic of Iran is one of the major powers in the Middle East. Since 1957, when nuclear energy program received technical assistance from the U.S., its successive leaders have eagerly pursued the policy for developing nuclear technology. The only exception took place during the early years of the Ayatollah Khomeni government when all nuclear program was temporarily suspended. Recent disclosures show that Iran has been conducting several covert nuclear programs, which is considered by the international community as a possible step toward nuclear weapons. This thesis first analyzes the background of Iran’s nuclear development, its motives, and the evolution of its nuclear development. The U.S., Russia, the PRC, and other related powers’ attitude toward Iran’s nuclear programs will be analyzed latter. Once Iran gets nuclear weapons, its impact on the security in the Middle East as well as on the nuclear non-proliferation regime will also be examined finally.

The promotion of sustainable development is an objective shared by African Union (AU) member states and the pursuance thereof is expressly mandated by the Constitutive Act of the African Union, 2000 and the Treaty Establishing the African Economic Community, 1992. Lack of access to modern energy sources, such as electricity and the heavy reliance on traditional biomass as primary energy source are factors contributing to the non-achievement of the promotion of sustainable development. These factors are collectively referred to as energy poverty. The African Continent as a whole has limited, and in some instances, lack access to modern energy sources while the majority of its population relies heavily on traditional biomass as primary energy source. Africa can accordingly be classified as an energy poor region–a situation which does not bode well for the promotion of sustainable development. Access to reliable, affordable, economically viable, socially acceptable and environmentally sound energy services and resources is fundamental to socio-economic development. Mitigating the impacts of energy poverty and more specifically lack of access to modern energy sources on the sustainable development of Africa depends upon ensuring increased access to modern energy sources. The above-mentioned instruments furthermore contain provisions which link regional cooperation on the formulation of coordinated regional law and policy on areas/matters of common concern with the achievement of the objective of promoting sustainable development in Africa. One of the areas of common concerns listed is that of energy. Regional cooperation must accordingly be geared towards the effective development of the continent‘s energy and natural resources; promoting the development of new and renewable energy in the framework of the policy of diversification of sources of energy; and establishing an adequate mechanism of concerted action and coordination for the collective solution of the energy development problems within the AU. The formulation of coordinated energy law and policy should take place with reference to the specific sources of energy to be regulated. In this regard, the provisions of the Abuja Treaty and other sub-regional energy access initiatives list various sources of energy as forming part of a diversified AU energy mix – one of which is nuclear energy. In this study recommendations are made as to what should be embodied in a coordinated AU regional nuclear legal framework aimed at regulating increased access to nuclear energy capable of contributing towards the promotion of sustainable development. The recommendations are based on an examination of relevant international, regional and sub-regional legal instruments and other initiatives. / PhD (Law), North-West University, Potchefstroom Campus, 2014

É presentada nesta dissertação uma análise espectral das equações de transporte de nêutrons, independente do tempo, em geometria unidimensional e bidimensional, na formulação de ordenadas discretas (SN), utilizando o modelo de uma velocidade e multigrupo, considerando meios onde ocorrem o fenômeno da fissão nuclear. Esta análise espectral constitui-se na resolução de problemas de autovalores e respectivos autovetores, e reproduz a expressão para a solução geral analítica local das equações SN (para geometria unidimensional) ou das equações nodais integradas transversalmente (geometria retangular bidimensional) dentro de cada região homogeneizada do domínio espacial. Com a solução geral local determinada, métodos numéricos, tais como os métodos de matriz de resposta SN, podem ser derivados. Os resultados numéricos são gerados por programas de computadores implementados em MatLab, versão 2012, a fim de verificar a natureza dos autovalores e autovetores correspondentes no espaço real ou complexo. / Presented in this dissertation is a spectral analysis of the neutron transport equations in the slab and X, Y geometry time-independent discrete ordinates formulation using the one-speed and multigroup model in neutron fission reacting media. This spectral analysis is bared on solving eigenvalue problems and yields the expression for the local general solution of the equations (for slab geometry) or of the transverse integrated nodal equations (for multidimensional rectangular geometry) within each homogenized region of the domain. With the local general solution so determined, a number of coarse-mesh numerical methods, such as the response matrix methods, can be derived. Numerical results are generated by computer program s implemented in MatLab, version 2012, in order to verify the nature of the eigenvalues and corresponding eigenvectors in real or complex space.

The insertion of Modern and Contemporary Physics (FMC) in High School (IN) supported by researchers from the School of Sciences and Physical Education is linked to a concern with the initial training and continuing education. In this paper, we present results of research through an undergraduate Supplementary Discipline (DCG), the initial training of teachers, aiming at achieving the contents of FMC Health and cross-cutting theme in the planning of teaching undergraduates in physics. The implementation of this discipline occurred in the 2nd half of 2011, the degree course in Physics UFSM. To produce this DCG was made a research on the topic Radioactivity and Nuclear Energy (EN / Rad) in major journals and conferences in the area of Science Education and Physical Education in the period 2005 to 2010. The results of this investigation, which have focused on the proposed training for the classroom, pointed a small number of implementations. We also carried out an analysis of the curriculum, the graduate courses in Physics at the federal universities of RS, especially UFSM, regarding the relationship of the disciplines of the grid that addressed the conceptual and procedural contents on the subject EN / Rad. In the analysis of documents were used content analysis procedures. The results of this analysis, from the perspective of National Curricular Guidelines (DCN) for courses in Physics, presented a temporal mismatch between these disciplines with differing emphasis. In this sense, the DCG has come to contribute to the Initial Training for the elaboration of didactic plans, relating the theme EN / Rad and Health, along activities for discussion and didactic plans, results pointing to the levels of coordination between these two themes. The main result was presented in planning the sequence and importance given to the Health theme in these relationships, demonstrating that the Health theme is used as an illustration, usually at the end of the planning, configuring itself as a weak link. / A inserção da Física Moderna e Contemporânea (FMC) no Ensino Médio (EM) defendida por pesquisadores das áreas de Ensino de Ciências e de Ensino de Física está vinculada a uma preocupação com a formação inicial e continuada de professores. Neste trabalho, apresentam-se resultados de pesquisa, através de uma Disciplina Complementar de Graduação (DCG), na formação inicial de professores, visando à articulação dos conteúdos de FMC e o tema transversal Saúde nos planejamentos didáticos dos licenciandos em Física. A implementação desta disciplina ocorreu no 2º semestre de 2011, no curso de licenciatura em Física da UFSM. Para a elaboração desta DCG foi realizada uma investigação sobre o tema Energia Nuclear e Radioatividade (EN/Rad) nos principais periódicos e eventos da área de Ensino de Ciências e Ensino de Física, no período de 2005 a 2010. Os resultados desta investigação, que tiveram como foco as propostas de ensino para a sala de aula, apontaram um número reduzido de implementações. Também foi realizada uma análise das grades curriculares, dos cursos de licenciatura em Física das universidades federais do RS, em especial da UFSM, quanto à relação das disciplinas da grade que contemplassem os conteúdos conceituais e procedimentais sobre o tema EN/Rad. Na análise dos documentos foram utilizados os procedimentos de análise de conteúdo. Os resultados desta análise, sob a ótica das Diretrizes Curriculares Nacionais (DCN) para os cursos de Física, apresentaram uma incompatibilidade temporal entre estas disciplinas de diferentes ênfases. Neste sentido, a DCG veio a contribuir na Formação Inicial para a elaboração de planejamentos didáticos, relacionando o tema EN/Rad e a Saúde, ao longo de atividades de discussão e de planejamentos didáticos, apontando como resultados os níveis de articulação entre estes dois temas. O principal resultado apresentado nos planejamentos foi a sequência e a relevância dada ao tema Saúde nestas relações, demonstrando que o tema Saúde é utilizado como uma ilustração, geralmente, ao final dos planejamentos, configurando-se como uma articulação frágil.

Thesis (MTech (Quality)--Cape Peninsula University of Technology, 2009 / There is a South African Government initiative to use State-owned Enterprises (SOE’s) to roll out a programme for the development and stimulation of local small businesses in South Africa. The state has requested SOE’s to set targets on a voluntary basis to increase trade with small businesses, with the purpose of developing small enterprises to eventually enhance skills transfer, training and employment. However, when large customers such as Eskom Nuclear Generation require ISO certification as a prerequisite for a supplier to provide goods and/or services to them, most small businesses are unable to comply. The requirement of ISO9000 compliance inhibits the ability of most small businesses to compete with their larger counterparts. Small businesses constitute as much as 90% of most world economies. They have many advantages to offer customers, such as a high level of flexibility, innovation and responsiveness to customer needs. These attributes can introduce healthy competition to the supply chain. Small businesses, by their very nature experience more risks, such as a higher vulnerability to volatile market forces and skills loss. In addition, they are generally less specialised. They are under continuous competitive pressure, and are generally not able to provide assurance of a sustainable product over a longer period. Although there is an imperative to develop and use small suppliers, they introduce higher risk to the supply chain. The primary research objective of this dissertation is to develop a robust model to identify risks inherent to small businesses, and to propose measures to mitigate such risks. A classification of problems with small suppliers that have occurred at Koeberg Nuclear Power Station over a period of 3 years (from June 2005 to May 2008), will form the basis of the research methodology. The anticipated findings of the research include the following. _ Several common critical issues of failure will be identified in the internal processes of small suppliers, with variations between types of suppliers, which will indicate which elements within the context of ISO9000 can be applied to address shortcoming in the suppliers’ processes. _ A matrix will be compiled from this by which the customer can identify the type of supplier, the types of risks inherent to that supplier, and which elements of ISO9000 the customer should insist upon to be adopted into an elementary quality management system of that small supplier. This should be executed as part of a larger supplier development programme.

É presentada nesta dissertação uma análise espectral das equações de transporte de nêutrons, independente do tempo, em geometria unidimensional e bidimensional, na formulação de ordenadas discretas (SN), utilizando o modelo de uma velocidade e multigrupo, considerando meios onde ocorrem o fenômeno da fissão nuclear. Esta análise espectral constitui-se na resolução de problemas de autovalores e respectivos autovetores, e reproduz a expressão para a solução geral analítica local das equações SN (para geometria unidimensional) ou das equações nodais integradas transversalmente (geometria retangular bidimensional) dentro de cada região homogeneizada do domínio espacial. Com a solução geral local determinada, métodos numéricos, tais como os métodos de matriz de resposta SN, podem ser derivados. Os resultados numéricos são gerados por programas de computadores implementados em MatLab, versão 2012, a fim de verificar a natureza dos autovalores e autovetores correspondentes no espaço real ou complexo. / Presented in this dissertation is a spectral analysis of the neutron transport equations in the slab and X, Y geometry time-independent discrete ordinates formulation using the one-speed and multigroup model in neutron fission reacting media. This spectral analysis is bared on solving eigenvalue problems and yields the expression for the local general solution of the equations (for slab geometry) or of the transverse integrated nodal equations (for multidimensional rectangular geometry) within each homogenized region of the domain. With the local general solution so determined, a number of coarse-mesh numerical methods, such as the response matrix methods, can be derived. Numerical results are generated by computer program s implemented in MatLab, version 2012, in order to verify the nature of the eigenvalues and corresponding eigenvectors in real or complex space.

Submitted by Leandro da Silva Batista Pereira (trabanddr@gmail.com) on 2013-10-22T13:51:08Z No. of bitstreams: 1 Dissertação Versão Final - 2.pdf: 1234281 bytes, checksum: 86be572fe83ef8688da681c95ba07ccb (MD5) / Approved for entry into archive by Rafael Aguiar (rafael.aguiar@fgv.br) on 2013-11-18T17:12:49Z (GMT) No. of bitstreams: 1 Dissertação Versão Final - 2.pdf: 1234281 bytes, checksum: 86be572fe83ef8688da681c95ba07ccb (MD5) / Approved for entry into archive by Marcia Bacha (marcia.bacha@fgv.br) on 2013-11-21T13:34:22Z (GMT) No. of bitstreams: 1 Dissertação Versão Final - 2.pdf: 1234281 bytes, checksum: 86be572fe83ef8688da681c95ba07ccb (MD5) / Made available in DSpace on 2013-11-21T13:39:14Z (GMT). No. of bitstreams: 1 Dissertação Versão Final - 2.pdf: 1234281 bytes, checksum: 86be572fe83ef8688da681c95ba07ccb (MD5) Previous issue date: 2013-08-27 / The present work covers the first years of the Brazilian nuclear policy, betwee n 1945 and 1956. Our aim is to understand the reasons of the triumph of Admiral Álvaro Alberto in the 1956 Parliamentarian Inquiry Commission of the Nuclear Question (CP I da Questão Nuclear), in which his policy proposals for the nuclear sector were vindicated and re-established, even after the personal defeats suffered by him during the Café Filho Administration (1954-1955), when he was fired from the presidency of the CNPq and witnessed his nuclear policy being stopped by the government. The work concludes that such an outcome was made possible by the fact that his guidelines for the nuclear sector managed to obtain a significant echo among several sectors of the Brazilian society that defended the state monopoly on the natural resources and an autonomous scientific and technological development effort. Besides that, his efforts were aided by an exceptionally favorable political conjuncture at the earl y phase of the Juscelino Kubitschek Administration (1956-1961), which was distinguished by a st rong political polarization, in which the nuclear question gained a national projec tion. With his triumph in the 1956 CPI, Alberto managed to define the terms of the debat e about the nuclear policy in the following years and decades. / Os primeiros anos da política nuclear brasileira, entre os anos de 1945 e 1956, é o assunto tratado no presente trabalho. Aqui procuramos compreender as razões por trás da vitória de Álvaro Alberto na CPI da Questão Nuclear de 1956, na qual as suas propostas para o setor foram valorizadas e restabelecidas, mesmo após o Almirante ter sofrido derrotas durante o governo Café Filho (1954-55), quando foi exonerado da presidência do CNPq e teve a sua política atômica suspensa. O trabalho conclui que a vitória foi possível graças ao fato de as suas diretrizes para a área nuclear terem ressonância junto a diversos setores da sociedade brasileira adeptos do monopólio estatal sobre os recursos naturais e de um desenvolvimento científico e tecnológico em bases autônomas; além de uma conjuntura política excepcional no início do governo de Juscelino Kubitschek, marcado por forte polarização política, na qual o assunto nuclear ganhou projeção nacional. Com a sua vitória na CPI de 1956, Álvaro Alberto logrou definir os termos debate sobre a política a ser adotada na área atômica pelos anos e décadas seguintes.

Le carbure de bore B4C est une céramique couramment utilisée comme absorbant neutronique pour la régulation de la puissance des réacteurs nucléaires. Les réactions d’absorption neutronique, de type (n,α) sur l’isotope bore-10, conduisent à la production de grandes quantités d’hélium (jusqu’à 1022.cm-3). Il en résulte du gonflement induit par la formation de bulles hautement pressurisées, puis de la microfissuration. L’analyse de la littérature montre que les mécanismes de diffusion de l’hélium et les premières étapes de la formation des bulles sont mal connus. L’objectif de notre étude est d’étudier le comportement de l’hélium dans le carbure de bore, en réalisant une analyse paramétrique. Pour cela, des échantillons de B4C fritté à partir de différentes poudres ont été implantés en hélium dans des accélérateurs d’ions à différentes concentrations et températures, ce afin de simuler l’hélium produit en réacteur. Les analyses se sont ensuite principalement appuyées sur deux techniques de caractérisation : L’analyse par réactions nucléaires ou NRA (Nuclear Reaction Analysis) qui est une technique d’analyse par faisceau d’ions. La réaction 3He(d,4He)1H utilisée permet d’obtenir des profils d’hélium dans le matériau. La Microscope Electronique en Transmission (MET) qui permet d’observer les amas potentiels d’hélium dans le matériau. Nous avons tout d’abord mis en évidence l’influence de la concentration d’hélium implanté : plus elle est élevée, plus la densité d’amas dans la zone implantée est élevée ; puis celle de de la température d’implantation : plus cette dernière est élevée, plus la température seuil de germination des amas est élevée et leur densité réduite. Nous en avons déduit que ces différences étaient dues à l’influence de l’endommagement résiduel, plus faible à haute température. Des doubles implantations d’or et d’hélium ont confirmé que l’endommagement créé par les ions Au avait un effet significatif sur la germination des amas, en abaissant le seuil de température de leur apparition et en augmentant leur densité. Ensuite, nous avons mis en évidence le rôle des joints de grains qui se sont révélés être de véritables pièges pour hélium. Nous avons démontré que l’hélium ne diffuse pas dans ni à travers ces joints de grains jusqu’à des températures de l’ordre de 1200°C. Enfin, l’élargissement des profils d’hélium après traitements thermiques, dans la gamme de température 600-800°C, a permis de déterminer un coefficient de diffusion apparent de l’hélium dans le B4C, paramètre inconnu dans la littérature, ainsi qu’une énergie d’activation : D = D0.exp(-Ea/kT), avec D0 = 6,03x10- 3 x/ 2,5 cm2.s-1 et Ea = 2,03 ±0,18 eV. L’ensemble de ce travail a permis de mieux appréhender le comportement de l’hélium dans le carbure de bore qui sera utilisé dans les dispositifs de contrôle de la puissance et les protections neutroniques du réacteur ASTRID, projet français de réacteur à spectre neutronique rapide refroidi au sodium. Les résultats obtenus permettent ainsi de tirer des indications utiles à la conception des éléments absorbants neutroniques du réacteur / Boron carbide B4C is a ceramic commonly used as a neutron absorber to control the power of nuclear power plants. The neutron absorption reactions, (n,α) type on the boron-10 isotope, lead to the production of large quantities of helium (up to 1022.cm-3). This results to swelling induced by the formation of highly pressurized bubbles, followed by microcracking. Analysis of the literature shows that helium diffusion mechanisms and the early stages of bubble formation are poorly understood. The goal of our work is to study the behaviour of helium in boron carbide, by carrying out a parametric analysis. For this purpose, samples of B4C, sintered from different powders, were implanted in helium with ion accelerators at different concentrations and temperatures, in order to simulate the helium produced in the reactor. The analyses were then mainly based on two characterization techniques: Nuclear Reaction Analysis (NRA), which is an ion beam analysis technique. The 3He(d,4He)1H reaction used allows obtaining helium profiles in the material. The Transmission Electron Microscope (TEM), which allows observation of potential helium clusters in the material. We first demonstrated the influence of the concentration of implanted helium: the higher it is, the higher the density of clusters in the implanted area; then the influence of the implantation temperature: the higher it is, the higher the threshold temperature for cluster nucleation and the lower the density. We have deduced that these differences were due to the influence of the residual damage, which is lower at high temperature. Dual gold and helium implantations confirmed that damage caused by Au ions had a significant effect on cluster nucleation, lowering the temperature threshold of their occurrence and increasing their density. Next, we have highlighted the role of grain boundaries which have proved to be very efficient traps for helium. We have demonstrated that helium does not diffuse into these grain boundaries at temperatures up to 1200°C. Finally, the broadening of the helium profiles after heat treatments, in the temperature range 600-800°C, allowed us to determine an apparent diffusion coefficient of helium in B4C, still unknown in the literature: D = D0.exp (-Ea/kT), with D0 = 6.03x10-3 x/ 2.5 cm2.s-1 and Ea = 2.03 ± 0.18 eV. This work allowed us to better understand the behaviour of helium in boron carbide, which will be used in power control devices and neutron protections for the ASTRID reactor, a French sodium fast-neutron reactor project. The results thus allow obtaining useful indications for the design of the neutron absorber elements of the reactor

The solution of large and sparse eigenvalue problems arising from the discretization of the diffusion equation is considered. The multigroup<p>diffusion equation is discretized by means of the Nodal expansion Method (NEM) [9, 10]. A new formulation of the higher order NEM variants revealing the true nature of the problem, that is, a generalized eigenvalue problem, is proposed. These generalized eigenvalue problems are solved using the Jacobi-Davidson (JD) method<p>[26]. The most expensive part of the method consists of solving a linear system referred to as correction equation. It is solved using Krylov subspace methods in combination with aggregation-based Algebraic Multigrid (AMG) techniques. In that context, a particular<p>aggregation technique used in combination with classical smoothers, referred to as oblique geometric coarsening, has been derived. Its particularity is that it aggregates unknowns that<p>are not coupled, which has never been done to our<p>knowledge. A modular code, combining JD with an AMG preconditioner, has been developed. The code comes with many options, that have been tested. In particular, the instability of the Rayleigh-Ritz [33] acceleration procedure in the non-symmetric case has been underlined. Our code has also been compared to an industrial code extracted from ARTEMIS. / Doctorat en Sciences de l'ingénieur / info:eu-repo/semantics/nonPublished