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1
Heywood, D. I. "Environmental radiation monitoring and the siting of nuclear facilities." Thesis, University of Newcastle Upon Tyne, 1987. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.382436.
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2
Åberg, Lindell Matilda. "Proliferation resistances of Generation IV recycling facilities for nuclear fuel." Licentiate thesis, Uppsala universitet, Tillämpad kärnfysik, 2013. http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-209098.
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The effects of global warming raise demands for reduced CO2 emissions, whereas at the same time the world’s need for energy increases. With the aim to resolve some of the difficulties facing today’s nuclear power, striving for safety, sustainability and waste minimization, a new generation of nuclear energy systems is being pursued: Generation IV. New reactor concepts and new nuclear facilities should be at least as resistant to diversion of nuclear material for weapons production, as were the previous ones. However, the emerging generation of nuclear power will give rise to new challenges to the international safeguards community, due to new and increased flows of nuclear material in the nuclear fuel cycle. Before a wide implementation of Generation IV nuclear power facilities takes place, there lies still an opportunity to formulate safeguards requirements for the next generation of nuclear energy systems. In this context, this thesis constitutes one contribution to the global efforts to make future nuclear energy systems increasingly resistant to nuclear material diversion attempts. This thesis comprises three papers, all of which concern safeguards and proliferation resistance in Generation IV nuclear energy systems and especially recycling facilities: In Paper I, proliferation resistances of three fuel cycles, comprising different reprocessing techniques, are investigated. The results highlight the importance of making group actinide extraction techniques commercial, due to the inherently less vulnerable isotopic and radiological properties of the materials in such processes. Paper II covers the schematic design and safeguards instrumentation of a Generation IV recycling facility. The identification of the safeguards needs of planned facilities can act as a guide towards the development of new instrumentation suitable for Generation IV nuclear energy systems. Finally, Paper III describes a mode of procedure for assessing proliferation resistance of a recycling facility for fast reactor fuel. The assessments may be used, as in this case, as an aid to maintain or increase the inherent proliferation resistance when performing facility design changes and upgrades.
3
Long, Jonathan. "A Safeguards Design Strategy for Domestic Nuclear Materials Processing Facilities." Digital Commons @ East Tennessee State University, 2010. https://dc.etsu.edu/etd/1710.
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The outdated and oversized nuclear manufacturing complex within the United States requires its transformation into a smaller, safe, and secure enterprise. Health and safety risks, environmental concerns, and the end of the Cold War have all contributed to this necessity. The events of September 11, 2001, emphasized the protection requirements for nuclear materials within the U.S. as well as abroad.
Current Nuclear Safeguards regulations contain minimal prescriptive requirements relating to the design of new production facilities. Project management and engineering design guides require that design documents contain specific and measureable statements relating to systems requirements. The systems engineering process evaluates alternatives for an effective and integrated solution during project design.
A Safeguards Design Strategy for domestic nuclear materials processing facilities based upon a core "framework" of safeguards regulatory programmatic elements that also use the prescriptive requirements and similar goals of safety, health, and physical security regulations is proposed and justifiable.
4
Folkert, Michael R. (Michael Ryan) 1975. "Monte Carlo simulation of neutron shielding for proton therapy facilities." Thesis, Massachusetts Institute of Technology, 1998. http://hdl.handle.net/1721.1/50492.
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Thesis (S.B. and S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1998.Includes bibliographical references (leaves 60-63).
A study was performed to develop a Monte Carlo method of modeling neutron shielding of proton therapy facilities in a complex, realistic environment. The bulk neutron shielding of the Northeast Proton Therapy Center (Massachusetts General Hospital, Boston, MA) was used as the basis of the design work. A geometrical model of the facility was simulated using the LAHET Code System, a set of Monte Carlo codes developed at Los Alamos National Laboratory. Additional software tools for reading and analyzing the simulation data that the model provides have been developed and tested. In order to verify the computer simulations, neutron detection and data acquisition systems have been assembled, modified, and thoroughly tested in order to monitor the neutron dose equivalent during proton beam operation at several locations on a continuous basis. Preliminary tests show that the geometry and physics models proposed in this work are valid.
by Michael R. Folkert.
S.B.and S.M.
5
Vadas, Jessica Elizabeth. "Probing the Fusion of Neutron-Rich Nuclei with Modern Radioactive Beam Facilities." Thesis, Indiana University, 2019. http://pqdtopen.proquest.com/#viewpdf?dispub=13423478.
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Fusion in neutron-rich environments is presently a topic of considerable interest. For example, the optical emission spectrum from the neutron star merger GRB170817A clearly establishes this neutron-rich environment as an important nucleosynthetic site. Fusion of neutron-rich light nuclei in the outer crust of an accreting neutron star has also been proposed as responsible for triggering X-ray super-bursts. The underlying hypothesis in this proposition is that the fusion of neutron-rich nuclei is enhanced as compared to stable nuclei. A good approach to understand how fusion proceeds in neutron-rich nuclei is to measure the fusion excitation function for an isotopic chain of nuclei. Modern radioactive beam facilities provide the opportunity to systematically address this question. An experimental program has been established to measure the fusion excitation function for light and mid-mass neutron-rich nuclei using low-intensity radioactive beams. The technique was initially demonstrated by measuring the fusion excitation functions for 18O and 19O nuclei incident on a 12C target. The beam of 19O ions was produced by the 18O(d,p) reaction with an intensity of 2-4 x 104 p/s at Florida State University. Evaporation residues resulting from the de-excitation of the fusion product were distinguished by measuring their energy and time-of-flight. To explore mid-mass neutron-rich nuclei much further from stability, the fusion excitation functions for 39,47K + 28Si were measured using the ReA3 reaccelerator facility at the National Superconducting Cyclotron Laboratory at Michigan State University. Incident ions were identified on a particle-by-particle basis by ΔE-TOF just upstream of the target. Fusion products were directly measured and identified by the E-TOF technique with an efficiency of ~70%. The measured fusion excitation functions for both the light and mid-mass systems have been compared to various theoretical models to elucidate how structure and dynamics impact the fusion of neutron-rich nuclei.
6
Fort, Emily Minatra. "A historical site assessment of the Georgia Tech Research Reactor." Thesis, Georgia Institute of Technology, 1999. http://hdl.handle.net/1853/17257.
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PERILLO, SERGIO R. P. "Determinacao do tempo de resposta de transdutores de pressao utilizando o metodo de medida direta." reponame:Repositório Institucional do IPEN, 1994. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10383.
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Dissertacao (Mestrado)
IPEN/D
Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP
8
Zhang, Youpeng. "Transmutation of Americium in Fast Neutron Facilities." Licentiate thesis, KTH, Reaktorfysik, 2011. http://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-31518.
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In this thesis, the feasibility to use a medium sized sodium cooled fast reactor fully loaded with MOX fuel for efficient transmutation of americium is investigated by simulating the safety performance of a BN600-type fast reactor loaded with different fractions of americium in the fuel, using the safety parameters obtained with the SERPENT Monte Carlo code. The focus is on americium mainly due to its long-term contribution to the radiotoxicity of spent nuclear fuel and its deterioration on core's safety parameters. Applying the SAS4A/SASSYS transient analysis code, it is demonstrated that the power rating needs to be reduced by 6% for each percent additional americium introduction into the reference MOX fuel, maintaining 100 K margin to fuel melting, which is the most limiting failure mechanism.Safety analysis of a new Accelerator Driven System design with a smaller pin pitch-to-diameter ratio comparing to the reference EFIT-400 design, aiming at improving neutron source efficiency, was also performed by simulating performance for unprotected loss of flow, unprotected transient overpower, and protected loss-of-heat-sink transients, using neutronic parameters obatined from MCNP calculations. Thanks to the introduction of the austenitic 15/15Ti stainless steel with enhanced creep rupture resistance and acceptable irradiation swelling rate, the suggested ADS design loaded with nitride fuel and cooled by lead-bismuth eutectic could survive the full set of transients, preserving a margin of 130 K to cladding rupture during the most limiting transient. The thesis concludes that efficient transmutation of americium in a medium sized sodium cooled fast reactor loaded with MOX fuel is possible but leads to a severe power penalty. Instead, preserving transmutation rates of minor actinides up to 42 kg/TWhth, the suggested ADS design with enhanced proton source efficiency appears like a better option for americium transmutation.QC 20110318
9
Rydell, Cecilia. "Seismic high-frequency content loads on structures and components within nuclear facilities." Licentiate thesis, KTH, Betongbyggnad, 2014. http://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-145403.
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Sweden is generally considered to be a low seismicity area, but for structures within nuclear power facilities, the safety level demand with respect to seismic events are high and thus, these structures are required to be earthquake-resistant. The seismic hazard is here primarily considered to be associated with near-field earthquakes. The nuclear power plants are further founded on hard rock and the expected ground motions are dominated by high frequencies. The design earthquake considered for the nuclear facilities has an annual probability of 10-5 events, that is, the probability of occurrence is once per 100 000 years. The focus of the study is the seismic response of large concrete structures for the nuclear power industry, with regard not only to the structure itself but also to non-structural components attached to the primary structure, and with emphasis on Swedish conditions. The aim of this licentiate thesis is to summarize and demonstrate some important aspects when the seismic load is dominated by high frequencies. Additionally, an overview of laws, regulations, codes, standards, and guidelines important for seismic analysis and design of nuclear power structures is provided. The thesis includes two case studies investigating the effect of seismic high-frequency content loads. The first study investigates the influence of gaps in the piping supports on the response of a steel piping system subjected to a seismic load dominated by high amplitudes at high frequencies. The gaps are found in the joints of the strut supports or are gaps between the rigid box supports and the pipe. The piping system is assessed to be susceptible to high-frequency loads and is located within the reactor containment building of a nuclear power plant. The stress response of the pipe and the acceleration response of the valves are evaluated. The second study investigates the effect of fluid-structure interaction (FSI) on the response of an elevated rectangular water-containing concrete pool subjected to a seismic load with dominating low and high frequencies, respectively. The pool is located within the reactor containment building of a boiling water reactor at a nuclear power plant. The hydrodynamic pressure distribution is evaluated together with the stress distribution in the walls of the tank. From the two case studies, it is evident that the response due to a seismic load dominated by high frequencies and low frequencies, respectively, is different. Although the seismic high-frequency load may be considered non-damaging for the structure, the effect may not be negligible for non-structural components attached to the primary structure. Including geometrical non-linear effects such as gaps may however reduce the response. It was shown that the stress response for most of the pipe elements in the first case study was reduced due to the gaps. It may also be that the inclusion of fluid-structure interaction effects changes the dynamic properties of a structural system so that it responds significantly in the high frequency range, thus making it more vulnerable to seismic loads dominated by high frequencies. In the second case study, it was shown that even for a seismic load with small amplitudes and short duration, but with dominating high-frequency content, as the Swedish 10-5 design earthquake, the increase of the dynamic response as fluid-structure interaction is accounted for is significant.QC 20150519
10
Dudar, Tamara Viktorivna, and Sergii Artseniovich Stankevich. "Geological environment capacity assessment in the vicinity of nuclear fuel cycle facilities." Thesis, SpaceConf-2016, 2016. http://er.nau.edu.ua/handle/NAU/22318.
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For the purpose of geoecological environment capacity assessment the authors
have produced a number of thematic landscape changes maps obtained as a result
of multispectral imagery processing, allowed assessing the state and trends in land
degradation processes within the territories of NPP and URF location. To continue
the research it is meant a deeper consideration of geology and geomorphology factors
together with soil, vegetation, land cover and land use ones taking into account the
radiation capacity factor for the territories of NFCF location. The results obtained are
supposed to show the impact assessments of vulnerability of the human-environment
system under such environmental changes.
11
Coelho, Joaquim Matheus Santiago. "Serrapilheira aplicada como biomonitor na avaliação do bosque urbano do Instituto de Pesquisas Energéticas e Nucleares, São Paulo,SP." Universidade de São Paulo, 2011. http://www.teses.usp.br/teses/disponiveis/85/85134/tde-24082012-162944/.
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Diversos processos são considerados responsáveis pela manutenção de ecossistemas. Entre eles podemos destacar a ciclagem mineral que corresponde ao ciclo dos elementos químicos que fluem entre os compartimentos bióticos, folhas e serrapilheira, e abióticos, atmosfera e solo. Esses elementos químicos se acumulam de forma ativa via absorção nos tecidos desses organismos, possibilitando sua aplicação como biomonitor na avaliação da qualidade do ambiente. Partindo dessa premissa é possível, a partir do estudo de ciclagem bioquímica de serrapilheira, conhecer a proveniência dos elementos químicos observados nas folhas diagnose das árvores. Este trabalho teve como objetivo avaliar, em escala espacial e temporal, as características da produção e sazonalidade da deposição da serrapilheira bem como estudar a composição química das folhas originadas desta serrapilheira depositada no campus do Instituto de Pesquisas Energéticas e Nucleares, IPEN, São Paulo, (RMSP) visando seu emprego como indicador do estagio de conservação ou degradação das áreas estudadas. Foram instalados 10 coletores de serrapilheira, com as dimensões de 1m x 1m, profundidade de 45 cm e 2 mm de malha, dispostos a 20 cm do solo sob a copa das árvores. Para determinação da produção de serrapilheira foram recolhidas deposições mensais nos coletores entre os meses: Fevereiro/2010 à Janeiro/2011. A determinação dos elementos químicos foi realizada utilizando as técnicas de fluorescência de raios-X por dispersão de comprimento de onda (WDXRF) e espectrometria de emissão ótica com fonte de plasma de argônio induzido (ICP-OES). Para a análise estatística dos dados foi aplicada a análise de componentes principais. A heterogeneidade temporal observada foi conseqüência da sazonalidade, interferindo na produção de serrapilheira em relação à quantidade e às porcentagens das frações. A produção de serrapilheira (base seca) durante o período de desenvolvimento da pesquisa foi de 5,86 Kg m-2 ano-1 sendo a espécie Psidiumguajara com maior índice de serrapilheira. Entre as frações, o compartimento folhas foi o mais representativo com 53,12% seguido do compartimento madeira com 26,84% e das partes reprodutivas que representou 20,04% de toda serrapilheira. Os elementos analisados foram Ca, Si, K, P, Fe Cl, Ni, Sr, Zn, Cu, Th, U, Mn, Al, Ti, Na, Mg, S e Br. Os elementos mais abundantes foram Ca, Si e K (1,8%, 0,5% e 0,6%, respectivamente) representando a composição foliar. Apesar de no passado ter havido unidades piloto de purificação de urânio e de tório, bem como considerando as atuais instalações do ciclo do combustível, foi observado que o material monitorado não se apresentou impactado quanto aos elementos químicos avaliados, e as instalações existentes não afetaram o ciclo biogeoquímico das plantas. O estudo trouxe resultados extremamente relevantes para se entender melhor em que estado se encontra o bosque em torno das instalações nucleares do IPEN/SP.Several processes are considered responsible for ecosystems maintaining. Among them we can highlight mineral cycling that corresponds to the cycle of chemical elements that flow between the biotic compartments, leaves and litterfall, and abiotic, atmosphere and soil. These chemical elements accumulate of the active form through the absorption in the tissues of these organisms, allowing its use as a use as biomonitor in the environment quality evaluation. Based on this premise it is possible, from the biochemical cycling study of litterfall, to know the origin of chemical elements observed in diagnosis leaves of trees. The objective of this study was evaluate, on spatial and temporal scale, the characteristics of the production and seasonality of the litterfall deposition and study the chemical composition of leaves arising from this litterfall deposited on the campus of the Nuclear and Energy Research Institute IPEN, São Paulo (RMSP), aiming the employment as an indicator of the conservation or degradation stage of the studies areas. Were installed 10 litterfall collectors, measuring 1m², depth of 45 cm and 2 mm mesh, placed at 20 cm from soil under the crown of 10 trees. To determinate the production of litterfall was collected the deposition monthly during the months of February/2010 through January/2011. The determination of chemical elements was realized by X-ray fluorescence for dispersion of wavelength (WDXRF) and inductively coupled plasma optical emission spectroscopy (ICP-OES). For the statistical analysis was applied to principal component analysis. The temporal heterogeneity observed was consequence of seasonality, interfering in the litterfall production relative to the amount and percentages of fractions. The production of litterfall (dry basis), during the development of the research was 5.86 kg m² year-1, being the Psidiumguajava species with the highest litterfall rate. Among the fractions, the most representative compartment was leaves with 53.12%, followed by wood with 26.84% and reproductive parts thats represented 20.04%, of all litterfall. The elements analyzed were Ca, Si, K, P, Fe Cl, Ni, Sr, Zn, Cu, Th, U, Mn, Al, Ti, Na, Mg, S e Br. The most abundant were Ca, Si, and K (1.8%, 0.5% and 0.6 respectively) representing the leaf composition. Although in the past have been pilot units of uranium and thorium purification, as well considering the current fuel cycle installations, it was observed that monitored material not be presented impacted as to the chemical elements evaluated, and the installations existing do not affect the biogeochemical cycle of plants. The study brought highly relevant results to better understand in what state is the forest around the nuclear facilities of IPEN/SP.
12
Lin, Hsun-Chia. "RELAP5 Model Benchmark for Thermal Performance of DRACS Test Facilities." The Ohio State University, 2016. http://rave.ohiolink.edu/etdc/view?acc_num=osu1462889408.
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KIIPPER, FELIPE de M. "Percepção pública das instalações nucleares." reponame:Repositório Institucional do IPEN, 2012. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10083.
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Dissertação (Mestrado)
IPEN/D
Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP
14
Ilina, Elena. "Understanding the application of knowledge management to the safety critical facilities." Doctoral thesis, KTH, Bro- och stålbyggnad, 2010. http://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-27608.
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Challenges to the operating nuclear power plants and transport infrastructures are outlined. It is concluded that most aggravating factors are related to knowledge. Thus, of necessity, effective knowledge management is required. Knowledge management theories are reviewed in their historical perspective as a natural extension and unification of information theories and theories about learning. The first line is identified with names as Wiener, Ashby, Shannon, Jaynes, Dretske, Harkevich. The second line – with Vygotsky, Engeström, Carayannis. The recent developments of knowledge management theorists as Davenport, Prusak, Drew, Wiig, Zack are considered stressing learning, retaining of knowledge, approaching the state awareness of awareness, and alignment of knowledge management with the strategy of the concerned organizations. Further, some of the details and results are presented of what is achieved so far. More specifically, knowledge management tools are applied to the practical work activities as event reporting, data collection, condition assessment, verification of safety functions and incident investigation. Obstacles are identified and improvements are proposed. Finally, it is advised to continue to implement and further develop knowledge management tools in the organizations involved in various aspects of safety critical facilities.Utmaningar som kärnkraftverken och transportinfrastrukturer står inför har kartlagts. Kartläggningen pekar på att problemen är relaterade till brister i kunskap. Det är därför nödvändigt att fokusera på kunskap och implementera kunskapsmanagement med däri ingående teorier. Sådana teorier beskrivs i ett historiskt perspektiv. Det framgår att kunskapsmanagement har flera rötter av vilka de viktigaste är informationsteorier och teorier om inlärning. Den första är associerad med namn som Wiener, Ashby, Jaynes, Dretske, Harkevich. Den andra med namn som Vygotsky, Engeström, Carayannis. Även bidrag från moderna tänkare inom kunskapsmanagement som Davenport, Prusak, Drew, Wiig, Zack utvärderas för att förstå hur de involverade organisationerna kontinuerligt kan lära sig, bevara kunskap, nå medvetande gällande kunskap och integrera kunskapsmanagement med företagsstrategier. Vidare så presenteras ett urval av resultat för att illustrera vad som har åstadkommits hittills. Kunskapsmanagement-teorier appliceras på verksamheter som erfarenhetsrapportering, databaser, provning, verifiering av säkerhetsfunktioner och utredning av incidenter. Kunskapsmanagement gör det möjligt att identifiera och beskriva brister i de etablerade verksamheterna och att föreslå förbättringar. Rekommendationen för framtiden är att fortsätta arbetet med implementering och vidareutveckling av kunskapsmanagement för applikationer som är relevanta för kärkraftverk, transportinfrastrukturer och andra säkerhetskritiska anläggningar.
QC 20101214
15
Carver, S. J. "Application of geographic information systems to siting radioactive waste disposal facilities." Thesis, University of Newcastle Upon Tyne, 1990. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.315467.
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Williams, Adam D. (Adam David) Ph D. Massachusetts Institute of Technology. "Beyond gates, guards and guns : the systems-theoretic framework for security at nuclear facilities." Thesis, Massachusetts Institute of Technology, 2018. https://hdl.handle.net/1721.1/122900.
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Thesis: Ph. D. Engineering Systems: Human-Systems Engineering, Massachusetts Institute of Technology, School of Engineering, Institute for Data, Systems, and Society, 2018Cataloged from PDF version of thesis.
Includes bibliographical references (pages 146-152).
Current approaches to nuclear security can produce elegantly designed physical protection systems (PPS) that may be limited by untenable assumptions or well stated-albeit vague and imprecise-descriptions of how to improve nuclear security culture itself. According to one nuclear security culture expert: While the International Atomic Energy Agency has released methodologies on evaluating vulnerabilities and physical protection, it has not yet introduced guidelines on assessing the human-factor in detection, delay, and response. (Khripunov, 2014, pp. 39-40) (Emphasis added) This dissertation argues that such a link lies in understanding how organizational influences affect the completion of tasks required for PPS to meet expected nuclear security performance goals. In this dissertation, I propose the System-Theoretic Framework for Security (the STFS) for evaluating system-level interactions between PPS and human/organizational behaviors to describe overall security performance.
Invoking key tenets of systems theory and organization science, the STFS uses the concept of "security task completion" to explain how the interactions between PPS and human/organizational behaviors result in security performance at nuclear facilities. Yet, empirical data is needed to explore the efficacy of this approach for incorporating organizational influences into security performance. As such, my research objectives were to: 1. Improve the understanding of how PPS and human/organizational behaviors interact to produce security performance at nuclear facilities, 2. Identify a manageable (but not exhaustive) set of organizational influences on this interaction, and 3. Develop a framework for assessing these interactions and organizational influences on security performance at nuclear facilities. I used a mixed methods research design to develop the STFS.
My first study consisted of 18 narrative interviews across different areas of nuclear security expertise and my second study examined the case of the 2012 security incident at the Y-12 National Security Complex. These two studies provided evidence for the security task completion construct (as a new causal mechanism), behavioral performance requirements (assumptions on which the causal mechanism is based), a set of organizational influences and quality indicators related to nuclear security performance. While this framework does not address every aspect of achieving high security performance, the STFS offers a structured thought process and direction for further development regarding how technologies and organizations interact to affect individual behaviors that contribute to security at nuclear facilities.
by Adam D. Williams.
Ph. D. Engineering Systems: Human-Systems Engineering
Ph.D.EngineeringSystems:Human-SystemsEngineering Massachusetts Institute of Technology, School of Engineering, Institute for Data, Systems, and Society
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MARCHESINI, PAULO R. de A. "Diagnóstico e sugestões para a gestão do conhecimento aplicada a uma instalação nuclear: a unidade de produção de hexafluoreto de urânio." reponame:Repositório Institucional do IPEN, 2008. http://repositorio.ipen.br:8080/xmlui/handle/123456789/11684.
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Dissertação (Mestrado)
IPEN/D
Instituto de Pesquisas Energéticas e Nucleares - IPEN/CNEN-SP
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Marins, Eugenio Rangel, and Instituto de Engenharia Nuclear. "Realidade virtual aplicada à proteção física de instalações nucleares." Instituto de Engenharia Nuclear, 2018. http://carpedien.ien.gov.br:8080/handle/ien/2652.
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Embora o Brasil não seja o típico alvo de ações terroristas, esse perigo não deve ser ignorado ou subestimado. Na nova ordem mundial, aqueles que se sentem ameaçados ou prejudicados algumas vezes abandonam as vias diplomáticas e recorrem a métodos não convencionais de resposta, que, por sua vez, podem resultar em atos de terrorismo. Com o aumento no número desse tipo de atentado em anos recentes, a importância da guarda e controle de materiais que possam ser usados em atos de terrorismo tomou uma dimensão mais relevante na atenção de governos, instituições e órgãos competentes pela salvaguarda de tais materiais. Por seu amplo potencial de causar prejuízos humanos, financeiros e morais, materiais nucleares e radioativos são o foco de programas e estratégias de salvaguardas com dimensões que vão desde as instituições individuais até o âmbito de organizações internacionais. O objetivo deste trabalho é investigar a integração das técnicas de Realidade Virtual ao planejamento das estratégias de proteção física a instalações nucleares e do treinamento da equipe que irá executá-las, de forma a evitar atos criminosos envolvendo materiais radioativos. Os resultados deste trabalho indicam que modelos virtuais de instalações nucleares podem auxiliar na elaboração e revisão das estratégias de proteção física e no treinamento das ações coordenadas das equipes de proteção física em emergências.
Although Brazil is not a typical target of terrorist action, this danger should not be ignored or underestimated. In the new world order, those who feel threatened or harmed sometimes abandon diplomatic ways and resort to unconventional methods of response, which can result in acts of terrorism. With the increasing number of such attacks in recent years, the importance of the custody and control of materials that can be used in acts of terrorism have taken a larger dimension in the attention of governments and institutions to the proper safeguard of these materials. Due to its great potential to cause human, financial and moral damages, nuclear and radioactive materials are the focus of safeguard programs and strategies, with dimensions ranging from individual institutions to the framework of international organizations. The objective of this work is to investigate the integration of Virtual Reality techniques in the planning of security strategies for nuclear installations and the training of the team that will execute them, in order to avoid criminal acts involving radioactive materials. The results of this work indicate that virtual models of nuclear installations can assist in the elaboration and revision of the security strategies and in the training of the coordinated actions of the physical protection teams in emergencies.
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Sinenian, Nareg. "Fast-ion spectrometry of ICF implosions and laser-foil experiments at the omega and MTW laser facilities." Thesis, Massachusetts Institute of Technology, 2013. http://hdl.handle.net/1721.1/80661.
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Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2013.Cataloged from PDF version of thesis. Page 224 blank.
Includes bibliographical references.
Fast ions generated from laser-plasma interactions (LPI) have been used to study inertial confinement fusion (ICF) implosions and laser-foil interactions. LPI, which vary in nature depending on the wavelength and intensity of the driver, generate hot electrons with temperatures ranging from tens to thousands of kilo-electron-volts. These electrons, which accelerate the ions measured in this work, can be either detrimental or essential to implosion performance depending on the ICF scheme employed. In direct-drive hot-spot ignition, hot electrons can preheat the fuel and raise the adiabat, potentially degrading compression in the implosion. The amount of preheat depends on the hot-electron source characteristics and the time duration over which electrons can deposit energy into the fuel. This time duration is prescribed by the evolution of a sheath that surrounds the implosion and traps electrons. Fast-ion measurements have been used to develop a circuit model that describes the time decay of the sheath voltage for typical OMEGA implosions. In the context of electron fast ignition, the produced fast ions are considered a loss channel that has been characterized for the first time. These ions have also been used as a diagnostic tool to infer the temperature of the hot electrons in fast-ignition experiments. It has also been shown that the hot-electron temperature scales with laser intensity as expected, but is enhanced by a factor of 2-3. This enhancement is possibly due to relativistic effects and leads to poor implosion performance. Finally, fast-ion generation by ultra-intense lasers has also been studied using planar targets. The mean and maximum energies of protons and heavy ions has been measured, and it has been shown that a two-temperature hot-electron distribution affects the energies of heavy ions and protons. This work is important for advanced fusion concepts that utilize ion beams and also has applications in medicine.
by Nareg Sinenian.
Ph.D.
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SANTOS, IVAN. "Descomissionamento de uma usina de producao de hexafluoreto de uranio." reponame:Repositório Institucional do IPEN, 2008. http://repositorio.ipen.br:8080/xmlui/handle/123456789/11758.
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Tese (Doutoramento)
IPEN/T
Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP
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LAINETTI, ELIZABETH B. de F. "Analise critica para adequacao fisica e implantacao de novos procedimentos na divisao de animais de laboratorios do IPEN." reponame:Repositório Institucional do IPEN, 2009. http://repositorio.ipen.br:8080/xmlui/handle/123456789/9442.
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Dissertacao (Mestrado)
IPEN/D
Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP
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Saurí, Suárez Héctor [Verfasser], and R. [Akademischer Betreuer] Stieglitz. "Individual dosimetry in disposal facilities for high-level nuclear waste / Héctor Saurí Suárez ; Betreuer: R. Stieglitz." Karlsruhe : KIT-Bibliothek, 2018. http://d-nb.info/1162540648/34.
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COSTA, ALESSANDRO M. da. "Metodos de calibracao e de intercomparacao de calibradores de dose utilizados em servicos de medicina nuclear." reponame:Repositório Institucional do IPEN, 1999. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10713.
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Dissertacao (Mestrado)
IPEN/D
Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP
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KIBRIT, EDUARDO. "Análise de requisitos normativos para o desenvolvimento e a implementação de um sistema de gestão da qualidade em instalações e atividades nucleares brasileiras." reponame:Repositório Institucional do IPEN, 2008. http://repositorio.ipen.br:8080/xmlui/handle/123456789/11605.
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Dissertação (Mestrado)
IPEN/D
Instituto de Pesquisas Energéticas e Nucleares - IPEN-CNEN/SP
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Eriksson, Daniel, and Tobias Gasch. "Load capacity of anchorage to concrete at nuclear facilities : Numerical studies of headed studs and expansion anchors." Thesis, KTH, Betongbyggnad, 2011. http://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-40820.
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The aim of this thesis was to study the load bearing capacity of anchor plates, used for anchorage to concrete located at nuclear facilities. Two different type of anchor plates were examined, which together constitute the majority of the anchor plates used at Forsmark nuclear facility in Sweden. The first is a cast-in-place anchor plate with headed studs and the second is a post-installed anchor plate which uses sleevetype expansion anchors. Hence, anchors with both a mechanical or a frictional interlock to the concrete were examined. The main analysis tool was the finite element method, through the use of the two commercially available software packages ABAQUS and ADINA and their non-linear material models for concrete and steel. As a first step, the numerical methods were verified against experimental results from the literature. However, these only concern single anchors. The results from the verifications were then used to build the finite element models of the anchor plates. These were then subjected to different load combinations with the purpose to find the ultimate load capacity. Failure loads from the finite element analyses were then compared to the corresponding loads calculated according to the new European technical specification SIS-CEN/TS 1992-4 (2009). Most of the failure loads from the numerical analyses were higher than the loads obtained from the technical specification, although in some cases the numerical results were lower than the technical specification value. However, many conservative assumptions regarding the finite element models were made, hence there might still be an overcapacity present. All analyses that underestimate the failure load were limited to large and slender anchor plates, which exhibit an extensive bending of the steel plate. The bending of the steel plate induce shear forces on the anchors, which leads to a lower tensile capacity. In design codes, which assume rigid steel plates, this phenomenon is neglected. The failure loads from all different load combinations analysed were then used to develop failure envelopes as a demonstration of a useful technique, which can be utilised in the design process of complex load cases.
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Durrant, Paul Timothy. "Development of EPSILON : a gamma ray imaging system for the nuclear industry." Thesis, University of Southampton, 1999. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.368122.
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LEVY, DENISE S. "Contribuição para informatização dos programas de proteção radiológica para instalações radiativas." reponame:Repositório Institucional do IPEN, 2012. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10144.
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Dissertação (Mestrado)
IPEN/D
Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP
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Chen, Yixue. "Coupled Monte Carlo discrete ordinates computational scheme for three-dimensional shielding calculations of large and complex nuclear facilities." Karlsruhe : FZKA, 2005. http://bibliothek.fzk.de/zb/berichte/FZKA7075.pdf.
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ROMANATO, LUIZ S. "Estudo de um casco nacional e sua instalacao para armazenagem seca de combustivel nuclear queimado gerado em reatores PWR." reponame:Repositório Institucional do IPEN, 2009. http://repositorio.ipen.br:8080/xmlui/handle/123456789/9476.
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Tese (Doutoramento)
IPEN/T
Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP
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GERULIS, EDUARDO. "Controle da dose de radiação ionizante para trabalhadores em uma instalação radiativa con fontes não-seladas." reponame:Repositório Institucional do IPEN, 2006. http://repositorio.ipen.br:8080/xmlui/handle/123456789/11408.
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Dissertacao (Mestrado)
IPEN/D
Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP
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LUCINIO, ELENA A. G. "Avaliacao das consequencias radiologicas de liberacoes rotineiras em sitio com varias intalacoes nucleares." reponame:Repositório Institucional do IPEN, 2003. http://repositorio.ipen.br:8080/xmlui/handle/123456789/11078.
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Dissertacao (Mestrado)
IPEN/D
Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP
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Bozzolan, Jean Claude. "Um estudo sobre o efeito dominó em instalações do ciclo do combustível nuclear." Universidade de São Paulo, 2006. http://www.teses.usp.br/teses/disponiveis/85/85133/tde-31052007-140555/.
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Os acidentes causados pelo efeito dominó são dos mais graves ocorridos na indústria química e de processo. Mesmo sendo o potencial destrutivo desses eventos acidentais bastante conhecido, pouca atenção tem sido dada a este problema pela literatura técnica e uma metodologia completa e aprovada para a avaliação quantitativa da contribuição do efeito dominó ao risco industrial ainda não está plenamente desenvolvida. O presente estudo propõe um procedimento sistemático para a avaliação quantitativa do efeito dominó em plantas químicas do ciclo do combustível nuclear. O trabalho é baseado em avanços recentes feitos na modelagem de danos a equipamentos de processo causados por incêndios e explosões devido aos vetores de propagação (radiação de calor, sobrepressão e projeção de fragmentos). Dados disponíveis na literatura técnica e novos modelos de vulnerabilidade deduzidos para diversas categorias de equipamentos de processo foram utilizados no presente trabalho. O procedimento proposto é aplicado a uma área de tancagem típica de uma planta de reconversão situada em um sítio que abriga varias outras instalações do ciclo do combustível nuclear. São analisados os vários eventos iniciadores, seus vetores de propagação, as conseqüências desses eventos e as freqüências associadas ao efeito dominó.Accidents caused by domino effect are among the most severe accidents in the chemical and process industry. Although the destructive potential of these accidental scenarios is widely known, little attention has been paid to this problem in the technical literature and a complete methodology for quantitative assessment of domino accidents contribution to industrial risk is still lacking. The present study proposed a systematic procedure for the quantitative assessment of the risk caused by domino effect in chemical plants that are part of nuclear fuel cycle plants. This work is based on recent advances in the modeling of fire and explosion damage to process equipment due to different escalation vectors (heat radiation, overpressure and fragment projection). Available data from literature and specific vulnerability models derived for several categories of process equipment had been used in the present work. The proposed procedure is applied to a typical storage area of a reconversion plant situated in a complex that shelters other nuclear fuel cycle facilities. The top-events and escalation vectors are identified, their consequences estimated and credible domino scenarios selected on the basis of their frequencies.
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LAURICELLA, CHRISTIANE M. "Analise de perigos em instalacoes de enriquecimento isotopico de uranio." reponame:Repositório Institucional do IPEN, 1998. http://repositorio.ipen.br:8080/xmlui/handle/123456789/9271.
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Dissertacao (Mestrado)
IPEN/D
Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP
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KUZNETSOV, OLEXIY. "Simulacao de danos e efeitos da radiacao em materiais estruturais." reponame:Repositório Institucional do IPEN, 1998. http://repositorio.ipen.br:8080/xmlui/handle/123456789/9269.
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Dissertacao (Mestrado)
IPEN/D
Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP
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Braidwood, David Walter. "Remediation and restoration of ocean exposed cliff-top, in the context of Dounreay (Scotland) nuclear power plant decommissioning." Thesis, University of Aberdeen, 2018. http://digitool.abdn.ac.uk:80/webclient/DeliveryManager?pid=237241.
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Restoration ecology continues to become ever more relevant as legislation demands we prevent biodiversity losses. Post-industrial restoration sites pose a number of additional challenges, including balancing ecological need with logistical and financial constraints. In the North of Scotland, one such site is the Dounreay Nuclear Power Plant, now undergoing decommissioning. The intention is to restore cliff-top habitat with native vegetation, blending in with its surroundings and necessitating minimal maintenance. The overall objective of this PhD research was to help develop a plan for the restoration of the site. A key challenge in this particular case was the residual low level radioactivity at depth in some areas, and a restoration layer is required to prevent contamination of bioreceptors at the surface, however, topsoil availability is limited. The cliff top site, and exposure to salt spray driven by strong winds, meant the identification of suitable vegetation communities for different areas could be crucial to its success. Vegetation and soil surveys across nine reference sites along the North coast of Scotland identified five non-peat vegetation communities suitable for Dounreay's restoration. Restoration ecology continues to become ever more relevant as legislation demands we prevent biodiversity losses. Post-industrial restoration sites pose a number of additional challenges, including balancing ecological need with logistical and financial constraints. In the North of Scotland, one such site is the Dounreay Nuclear Power Plant, now undergoing decommissioning. The intention is to restore cliff-top habitat with native vegetation, blending in with its surroundings and necessitating minimal maintenance. The overall objective of this PhD research was to help develop a plan for the restoration of the site. A key challenge in this particular case was the residual low level radioactivity at depth in some areas, and a restoration layer is required to prevent contamination of bioreceptors at the surface, however, topsoil availability is limited. The cliff top site, and exposure to salt spray driven by strong winds, meant the identification of suitable vegetation communities for different areas could be crucial to its success. Vegetation and soil surveys across nine reference sites along the North coast of Scotland identified five non-peat vegetation communities suitable for Dounreay's restoration. This prompted the development of a novel concept: that of utilising restoration sites as 'protorefuges' or 'protorefugia', i.e. restoration sites where threatened species at the leading edge of climate change can be translocated ahead of the climate changing. There, they would be joined by individuals of the wider population naturally dispersed as the climate shifts. Overall, these results enabled the development of a refined restoration plan for Dounreay, which takes into account the particular setting, constraints and timelines involved. With the decommissioning of an increasing number of nuclear sites across Britain and Europe taking place in the coming years, this research should be developed further. In particular our novel concept of protorefugia could even be put into practice, benefiting both restoration and conservation.
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MIORANZA, CLAUDIO. "Desenvolvimento e aplicacao de modelo multidimensional para a avaliacao da qualidade educacional no programa de pos-graduacao stricto sensu do IPEN." reponame:Repositório Institucional do IPEN, 2009. http://repositorio.ipen.br:8080/xmlui/handle/123456789/9492.
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Tese (Doutoramento)
IPEN/T
Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP
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Abuzohri, Ahmed, and Zlatko Dizdarevic. "Skapa öppenhet i erfarenhetsregistrering vid Forsmarks Kraftgrupp AB." Thesis, Uppsala universitet, Institutionen för teknikvetenskaper, 2012. http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-181620.
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Denna rapport är resultatet av ett examensarbete som utfördes på Forsmarks kärnkraftverk åt FTQ-avdelningen. FTQ-avdelning på Forsmark ansvarar för erfarenhetsåterföringens ärenden på anläggningen och försörjer organisationen med nya infallsvinklar gällande erfarenhetsåterföringstekniken. För cirka 10 år kom Forsmarks kraftgrupp AB till insikt att det fanns ett behov av att införa en aktiv erfarenhetsåterföringsprocess för att undvika upprepade misstag. Detta resulterade i att en ny avdelning skapades år 2008 med namnet FTQ. Denna avdelning skapade en databas med namnet ERFKA där man började samla in och lagra erfarenhetsåterföringsärenden. Dessutom innehåller ERFKA ett presentationsverktyg som möjliggör för personalen på FTQ-avdelningen att få fram grafisk statistik på allt som finns i databasen, som t.ex. statistik på tillbud, olyckor, månadsrapporter, rapporter mm. ERFKA-systemet uppfyller sitt syfte i detta sammanhang, men är på grund av sekretesskäl endast tillgänglig för ett tiotal personer. Det resulterar i att FTQ-avdelningen kontaktas för att ta fram informationen åt andra på anläggningen vilket både är tidskrävande och krångligt i en stor organisation som Forsmark. Examensjobbet mål var att skapa öppenhet i ERFKA-systemet. Genom att använda befintliga IT- verktyg utöver ERFKA ska informationen i ERFKA göras tillgänglig för alla på Forsmark. Examensarbetet består av två delar. Den ena består av framtagning och bearbetning av information från användare av ERFKA och den andra av framtagande av lösningförslag. I första delen utfördes intervjuer för att kartlägga vilken information som ska göras tillgänglig för personalen. Intervjuer hölls med de personer som var mest insatta i erfarenhetsåterföringsförbättringen och därmed var projektets främsta intressenter. I den andra delen togs det fram en kopplingsmodell för att presentera informationen från ERFKA på Forsmarks interna webbplats "Canalen". På grund av begränsad åtkomst till ERFKA för samtaliga anställda blev lösningen att flytta informationen från ERFKA till ett redan beprövat grafritandestatistikprogram med namnet Bi-Cycle. Detta program är tillgänglig för alla i organisationen, enligt bestämda specifikationer. Under projektets gång skapades ett schema på en möjlig kopplingsmodell där alla steg i kommunikationen visas tydligt. Modellen inkluderar allt från Canalen och grafer i Bi-Cycle till den slutgiltiga rapporten och några möjliga kopplingsmodeller mellan ERFKA och Bi-CycleThis project is a thesis work conducted at the Forsmark nuclear power plant at the FTQ department. The FTQ department at Forsmark is responsible for the experience feedback cases in the facility and supplying the organization with new insights regarding experience feedback techniques. About 10 years ago Forsmark Power Group Ltd realized the need to introduce an active experience feedback process to avoid repeating mistakes. This resulted in a creation of a new department in 2008 with the name of FTQ. Later, the FTQ department created a system with a database named ERFKA where all experience feedback cases have been collected and stored. In addition to the ERFKA database, the system contains a presentation tool that enables data in the database to be presented graphically at the FTQ department, such as statistics on incidents, accidents, monthly reports, reports and more. The ERFKA-system fulfills its purpose in this context but for safety reasons it is only available for approximately 15 people. It results in that FTQ department always needs to be contacted to develop information to others in the facility which is time-consuming and complicated in a big organization like Forsmark. The thesis project was focused in creating openness in the ERFKA-system with regard to safety aspects in the facility. By simply making the information in ERFKA available for everyone at Forsmark, without having to contact the FTQ department, and simultaneously use the tools that already are available on the power plant was this project carried out. The first part was accomplished by interviews in an attempt to specify the information types that were desired to be available. In pursuit of this information, we interviewed those people who were most familiar with the experience feedback improvement and could have most influence on the results. The second part was carried out through developing an acceptable proposed solution for a connection model to present information on the Forsmark intranet “Canalen” using those available tools. Due to the security limits in the facility, just few administrators can access the ERFKA. Therefore, the solution has been formed to transfer information from ERFKA to an already proven statistics and graph generating program called Bi-Cycle, which is available for all employees in the organization. During the project, a diagram of a possible link model has been created where all parts of the communication are clearly displayed. The model includes every detailed section beginning with Canalen, graphs in Bi-Cycle and ending with the final report.
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Apolevič, Jolanta. "The Impact of the Principles of International Environmental Law on Nuclear Law." Doctoral thesis, Lithuanian Academic Libraries Network (LABT), 2014. http://vddb.library.lt/obj/LT-eLABa-0001:E.02~2014~D_20140922_141136-97141.
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The thesis presents an investigation of the direct and indirect impact of environmental legal principles on international nuclear law and the regulation of nuclear activities, seeking to offer an up-to-date material for decision-making institutions and society on the main challenges that are necessary to overcome in order to reach the situation where nuclear energy could in the most effective way contribute to the implementation of environmental aims and where the environment could be adequately protected against any risks of the possible transboundary damage caused by nuclear activities developed for peaceful purposes (the analysis carried out in the thesis adopts an ecocentric rather than anthropocentric approach). The environmental legal principles chosen as an object for the analysis are those that provide for the guidelines and directions for the development of the international norms of nuclear law as well as lay down the regime for protecting natural environment (environmental safeguards) and international liability for environmental damage caused as a result of nuclear activities (i.e., the principles of cooperation, sustainable development, prevention, precaution, polluter pays, and the principle of information). After defining the points of interaction between international environmental law and nuclear law, the analysis proceeds with the examination of problems related to the evolution of environmental legal principles and their perspectives in the area of the... [to full text]Disertacijoje nagrinėjama tiesioginė ir netiesioginė aplinkos teisės principų įtaka tarptautinei branduolinei teisei ir branduolinės energetikos objektų reguliavimui, siekiant informuoti sprendimus priimančias institucijas ir visuomenę apie pagrindinius iššūkius, kuriuos reikia įveikti siekiant, kad branduolinė energetika kiek įmanoma veiksmingiau prisidėtų įgyvendinant aplinkosauginius tikslus, o aplinka būtų tinkamai apsaugota nuo taikiais tikslais vystomos branduolinės veiklos keliamos tarpvalstybinės žalos rizikos (analizės metu vyrauja ekocentrinis, o ne antropocentrinis požiūris). Analizės objektu pasirinkti tie aplinkos teisės principai, kurie numato gaires tarptautinėms branduolinės teisės normoms plėtotis, nustato gamtos apsaugos režimą (saugiklius) bei tarptautinę atsakomybę, atsirandančią dėl branduolinės energetikos objektų sukelto žalingo poveikio aplinkai (t.y. bendradarbiavimo, darnaus vystymosi, prevencijos, atsargumo, teršėjas moka ir informavimo principai). Nurodžius tarptautinės aplinkos teisės ir branduolinės teisės sąlyčio taškus, toliau nagrinėjamos problemos dėl aplinkos teisės principų raidos ir perspektyvų branduolinės energetikos objektų reglamentavimo srityje, pateikiama susijusi nacionalinių ir tarptautinių ginčų sprendimo institucijų dėl branduolinės energetikos objektų praktika, atsakoma į klausimą, kuris iš minėtų aplinkos teisės principų veikimo modelių – tiesioginis ar netiesioginis – yra veiksmingesnis siekiant įgyvendinti užsibrėžtus... [toliau žr. visą tekstą]
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Borsoi, Sad Sandrini. "Coordenação de dispositivos de proteção contra surtos em baixa tensão: ênfase instalações nucleares." Universidade de São Paulo, 2017. http://www.teses.usp.br/teses/disponiveis/3/3143/tde-27022018-082038/.
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O trabalho apresenta uma metodologia aplicável à coordenação de dispositivos de proteção contra surtos em sistemas de corrente alternada de baixa tensão. Esta tem como base a adequação dos níveis de isolamento e imunidade dos equipamentos elétricos e eletrônicos e de energia absorvida pelos dispositivos de proteção. A principal motivação está relacionada aos critérios de segurança e confiabilidade requeridos por instalações nucleares, em que a coordenação da proteção contra surtos assume um importante papel. Uma metodologia interativa é implementada visando otimizar o processo de análise e especificação dos dispositivos de proteção, considerando a adoção de métodos analíticos e numéricos. Modelos de equipamentos elétricos e eletrônicos, quando submetidos a surtos de tensão e corrente, além dos dispositivos de proteção contra surtos, são implementados no simulador de transitórios eletromagnéticos - ATP. Destacam-se nestes estudos, as análises de configurações e arranjos do sistema elétrico, assim como seus parâmetros, a influência destes na configuração ou arranjo ótimo dos dispositivos de proteção, além do atendimento aos requisitos das normas aplicáveis.The work presents a methodology regarding to low-voltage surge protective device coordination. This is based on adequacy of the isolation and immunity level of electrical and electronic equipment and the energy absorbed by the protective devices. The main motivation is related to the required nuclear plant reliability and safety criteria, in whose the surge protection coordination can assume an important role. An interactive methodology is carried out to optimize the analysis and the protection device specification, considering the adoption of analytical and numerical methods. Electrical and electronic equipment models, when submitted to voltage and current surges, in addition to surge protective devices, are implemented in the electromagnetic transient simulator - ATP. In these studies, the analysis of electrical system configurations and arrangements, as well as their parameters, and their influence on the configuration or optimum protective device arrangement, besides compliance with the requirements of applicable standards are highlighted.
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Chen, Yixue [Verfasser]. "Coupled Monte Carlo discrete ordinates computational scheme for three-dimensional shielding calculations of large and complex nuclear facilities / Forschungszentrum Karlsruhe GmbH, Karlsruhe. Yixue Chen." Karlsruhe : FZKA, 2005. http://d-nb.info/975460641/34.
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Zhuk, Alesia. "Does international human rights law impose constraints on digital manipulation or other cyberwarfare ruses? Analysis of the stuxnet worm attack on iranian nuclear facilities." Tesis, Universidad de Chile, 2017. http://repositorio.uchile.cl/handle/2250/170163.
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Tesis (magíster en derecho económico, inversiones, comercio y arbitraje internacional) Universidad de Chile, Universidad de HeidelbergIn 2010 a malicious computer worm attacked Iranian nuclear facilities in Natanz. It was the first computer worm that caused physical damage, and because of this, Iran had to suspend its nuclear program approximately for two years. The case caused great concern among the international community and raised the issue of protecting the population. This paper will address the issues of cyber war and its relationship with International Humanitarian Law and International Human Rights Law.
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MATTOS, LUIS A. T. de. "Proposta metodológica para a identificação e avaliação de aspectos e impactos ambientais em instalações nucleares do IPEN: estudo de caso aplicado ao Centro do Combustível Nuclear." reponame:Repositório Institucional do IPEN, 2013. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10595.
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Tese (Doutoramento)
IPEN/T
Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP
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ALVES, ALICE dos S. "Estudo dos agentes de risco ocupacional e seus prováveis agravos na saúde humana." reponame:Repositório Institucional do IPEN, 2015. http://repositorio.ipen.br:8080/xmlui/handle/123456789/25321.
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Dissertação (Mestrado em Tecnologia Nuclear)
IPEN/D
Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP
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Toppila, Timo, Ulrich Rohde, Bengt Hemström, Yuri Bezrukov, and Sören Kliem. "The European project FLOMIX-R: Description of the slug mixing and buoyancy related experiments at the different test facilities(Final report on WP 2)." Forschungszentrum Dresden, 2010. http://nbn-resolving.de/urn:nbn:de:bsz:d120-qucosa-28632.
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The goal of the work described in this report was the experimental investigation of the mixing of coolant with different quality (temperature, boron concentration) in nuclear reactors on the way from the cold leg through the downcomer and lower plenum to the core inlet in a systematic way. The obtained data were used for the clarification of the mixing mechanisms and form a data basis for the validation of computational fluid dynamics (CFD) codes. For these purposes, experiments on slug mixing have been performed at two test facilities, modelling different reactor types in scale 1:5, the Rossendorf and Vattenfall test facilities. The corresponding accident scenario is the start-up of first main coolant pump (MCP) after formation of a slug of lower borated water during the reflux-condenser mode phase of a small break loss of coolant accident (LOCA). The matrices for the experiments were elaborated on the basis of the key phenomena, being responsible for the coolant mixing during pump start-up. Slug mixing tests have also been performed at the VVER-1000 facility of EDO Gidropress to meet the specifics of this reactor type. The mixing of slugs of water of different quality is also very important for pre-stressed thermal shock (PTS) situations. In emergency core cooling (ECC) situations after a LOCA, cold ECC water is injected into the hot water in the cold leg and downcomer. Due to the large temperature differences, thermal shocks are induced at the reactor pressure vessel (RPV) wall. Temperature distributions near the wall and temperature gradients in time are important to be known for the assessment of thermal stresses. One of the important phenomena in connection with PTS is thermal stratification, a flow condition with a vertical temperature profile in a horizontal pipe. Due to the fluctuating character of the flow, this may cause thermal fatigue in the pipe. Besides of thermal fatigue, a single thermal shock can also be relevant for structural integrity, if it is large enough, especially in the case, that the brittle fracture temperature of the RPV material is reduced due to radiation embrittlement. Therefore, additional to the investigations of slug mixing during re-start of coolant circulation, the mixing of slugs or streams of water with higher density with the ambient fluid in the RPV was investigated. The aim of these investigations was to study the process of turbulent mixing under the influence of buoyancy forces caused by the temperature differences. Heat transfer to the wall and thermal conductivity in the wall material have not been considered. Experiments on density driven mixing were carried out at the Rossendorf and the Fortum PTS facilities.
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Toppila, Timo, Ulrich Rohde, Bengt Hemström, Yuri Bezrukov, and Sören Kliem. "The European project FLOMIX-R: Description of the slug mixing and buoyancy related experiments at the different test facilities(Final report on WP 2)." Forschungszentrum Rossendorf, 2005. https://hzdr.qucosa.de/id/qucosa%3A21690.
Full textAbstract:
The goal of the work described in this report was the experimental investigation of the mixing of coolant with different quality (temperature, boron concentration) in nuclear reactors on the way from the cold leg through the downcomer and lower plenum to the core inlet in a systematic way. The obtained data were used for the clarification of the mixing mechanisms and form a data basis for the validation of computational fluid dynamics (CFD) codes. For these purposes, experiments on slug mixing have been performed at two test facilities, modelling different reactor types in scale 1:5, the Rossendorf and Vattenfall test facilities. The corresponding accident scenario is the start-up of first main coolant pump (MCP) after formation of a slug of lower borated water during the reflux-condenser mode phase of a small break loss of coolant accident (LOCA). The matrices for the experiments were elaborated on the basis of the key phenomena, being responsible for the coolant mixing during pump start-up. Slug mixing tests have also been performed at the VVER-1000 facility of EDO Gidropress to meet the specifics of this reactor type. The mixing of slugs of water of different quality is also very important for pre-stressed thermal shock (PTS) situations. In emergency core cooling (ECC) situations after a LOCA, cold ECC water is injected into the hot water in the cold leg and downcomer. Due to the large temperature differences, thermal shocks are induced at the reactor pressure vessel (RPV) wall. Temperature distributions near the wall and temperature gradients in time are important to be known for the assessment of thermal stresses. One of the important phenomena in connection with PTS is thermal stratification, a flow condition with a vertical temperature profile in a horizontal pipe. Due to the fluctuating character of the flow, this may cause thermal fatigue in the pipe. Besides of thermal fatigue, a single thermal shock can also be relevant for structural integrity, if it is large enough, especially in the case, that the brittle fracture temperature of the RPV material is reduced due to radiation embrittlement. Therefore, additional to the investigations of slug mixing during re-start of coolant circulation, the mixing of slugs or streams of water with higher density with the ambient fluid in the RPV was investigated. The aim of these investigations was to study the process of turbulent mixing under the influence of buoyancy forces caused by the temperature differences. Heat transfer to the wall and thermal conductivity in the wall material have not been considered. Experiments on density driven mixing were carried out at the Rossendorf and the Fortum PTS facilities.
46
Struwe, Harald. "Spectrometry for the assessment of uranium contamination in buildings." Thesis, Imperial College London, 1998. http://hdl.handle.net/10044/1/8693.
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MARIN, MARISTHELA P. de A. "Analise de perigos em uma instalacao de producao de hexafluoreto de uranio." reponame:Repositório Institucional do IPEN, 1999. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10763.
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Dissertacao [Mestrado]
IPEN/D
Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP
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BAPTISTA, FILHO BENEDITO D. "Redes neurais para controle de sistemas de reatores nucleares." reponame:Repositório Institucional do IPEN, 1998. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10723.
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Tese (Doutoramento)
IPEN/T
Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP
49
Yi, Peng. "Iodine Isotopes (129I and 127I) in the Baltic Sea : Tracer applications & environmental impact." Doctoral thesis, Uppsala universitet, Luft-, vatten och landskapslära, 2012. http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-182357.
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129I is a radioactive isotope (T1/2= 15.7 million years) produced through natural and anthropogenic pathways, but the anthropogenic production is presently dominating the Earth’s surface environments. Sparse data from previous investigations in the Baltic Sea clearly indicated the occurrence of 129I at levels 3-4 orders higher than natural pre-atomic era (before 1940) without comprehensive evaluation of distribution and inventory. In this thesis extensive data on the distribution and inventory of iodine isotopes, 129I and 127I, and their species in waters of the Baltic Sea, Kattegat and Skagerrak are presented and used for estimation of water masses exchange and impact on the environment. To fulfill these objectives seawater samples were collected in August 2006 and April 2007 in the Baltic Proper, Kattegat and Skagerrak as well as in December 2009 in the Bothnian Sea. After elaborative chemical separation of total iodine and iodine species, the analysis was performed using ICP-MS for 127I and AMS for 129I. The results reveal considerable differences in 129I concentration in terms of spatial and temporal variability and expose relatively high concentrations in the deep waters. Inventory estimates show higher amounts of 129I in August 2006 (24.2 ±15.4 kg) than in April 2007 (14.4± 8.3 kg) within the southern and central Baltic Proper, whereas almost a constant inventory is found in the Kattegat Basin. Relatively high 127I-/127IO3- and 129I-/129IO3- values in water of the Baltic Proper suggest effective reduction of iodate at a maximum rate of 8×10-7 (127IO3-) and 6×10-14 (129IO3-) (g/m3.day). The combination of 129I and 127I as tracers of water circulation in the Baltic Sea suggest that upwelling deep basinal water occurs into the surface along the Gotland deep and intrusion of North Atlantic water into southern Baltic. Furthermore, 129I-based model inventory reveals inflow of 330 km3/y (230-450 km3/y) water from the Kattegat into the Baltic Proper. Water exchange between the Baltic Proper and the Bothnian Sea and vice versa is estimated at 980 km3/y (600-1400 km3/y) and 1180 km3/y (780-1600 km3/y) respectively. Finally, an environmental assessment of radioactivity associated with 129I burden in the Baltic Sea region is discussed.
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COELHO, JOAQUIM M. S. "Serrapilheira aplicada como biomonitor na avaliação do bosque urbano do Instituto de Pesquisas Energéticas e Nucleares, São Paulo, SP." reponame:Repositório Institucional do IPEN, 2012. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10108.
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Dissertação (Mestrado)
IPEN/D
Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP