Diseño del curso para operador "Coeficientes inherentes de reactividad" a plataforma e-Learning

Las centrales nucleares necesitan de personal altamente especializado y formado. Es por ello por lo que el sector de la formación especializada en centrales nucleares necesita incorporar los últimos avances en métodos formativos. Existe una gran cantidad de cursos de formación presenciales y es necesario transformar dichos cursos para utilizarlos con las nuevas tecnologías de la información. Para ello se necesitan equipos multidisciplinares, en los que se incluyen ingenieros, que deben identificar los objetivos formativos, competencias, contenidos y el control de calidad del propio curso. En este proyecto se utilizan técnicas de ingeniería del conocimiento como eje metodológico para transformar un curso de formación presencial en formación on-line a través de tecnologías de la información. En la actualidad, las nuevas tecnologías de la información y comunicación están en constante evolución. De esta forma se han sumergido en el mundo transformando la visión que teníamos de éste para dar lugar a nuevas oportunidades. Es por ello que este proyecto busca la unión entre el e-learning y el mundo empresarial. El objetivo es el diseño, en plataforma e-learning, de un curso técnico que instruya a operadores de sala de control de una central nuclear. El trabajo realizado en este proyecto ha sido, además de transformar un curso presencial en on-line, en obtener una metodología para que otros cursos se puedan transformar. Para conseguir este cometido, debemos preocuparnos tanto por el contenido de los cursos como por su gestión. Por este motivo, el proyecto comienza con definiciones básicas de terminología propia de e-learning. Continúa con la generación de una metodología que aplique la gestión de conocimiento para transformar cualquier curso presencial a esta plataforma. Definida la metodología, se aplicará para el diseño del curso específico de Coeficientes Inherentes de Reactividad. Finaliza con un estudio económico que dé viabilidad al proyecto y con la creación de un modelo económico que estime el precio para cualquier curso futuro. Abstract Nuclear power plants need highly specialized and trained personnel. Thus, nuclear power plant Specialized Training Sector requires the incorporation of the latest advances in training methods. A large array of face-to-face training courses exist and it has become necessary to transform said courses in order to apply them with the new information systems available. For this, multidisciplinary equipment is needed where the engineering workforce must identify educational objectives, competences and abilities, contents and quality control of the different courses. In this project, knowledge engineering techniques are employed as the methodological axis in order to transform a face-to-face training course into on-line training through the use of new information technologies. Nowadays, new information and communication technologies are in constant evolution. They have introduced themselves into our world, transforming our previous vision of them, leading to new opportunities. For this reason, the present Project seeks to unite the use of e-learning and the Business and Corporate world. The main objective is the design, in an e-learning platform, of a technical course that will train nuclear power plant control-room operators. The work carried out in this Project has been, in addition to the transformation of a face-to-face course into an online one, the obtainment of a methodology to employ in the future transformation of other courses. In order to achieve this mission, our interest must focus on the content as well as on the management of the various courses. Hence, the Project starts with basic definitions of e-learning terminology. Next, a methodology that applies knowledge management for the transformation of any face-to-face course into e-learning has been generated. Once this methodology is defined, it has been applied for the design process of the Inherent Coefficients of Reactivity course. Finally, an economic study has been developed in order to determine the viability of the Project and an economic model has been created to estimate the price of any given course

Sistemas de salvaguardia en reactores EPR

En este documento se describe brevemente el funcionamiento de los diversos sistemas de una planta nuclear operada con un reactor de tipo PWR. Más concretamente, el proyecto se centra en una descripción exhaustiva de los sistemas de salvaguardia y seguridad que regulan el funcionamiento de un reactor de tipo EPR, así como la central nuclear que contiene a dicho reactor. El proceso ha consistido en clasificar y resumir los distintos sistemas que operan en dicha planta, estudiando sus características y parámetros de funcionamiento. También se han estudiado los accidentes más comunes que pueden tener lugar en este tipo de centrales nucleares. Tras el análisis y estudio realizado acerca del reactor EPR, se puede concluir que las centrales nucleares que operan con este tipo de reactor experimentan una serie de mejoras en cuanto a la prevención de accidentes, así como una serie de mejoras de diseño en una gran variedad de sistemas y elementos del reactor, como pueden ser la vasija, los SG, etc. ABSTRACT This document gives a brief description of the operation of several systems of a nuclear power plant operating with a PWR reactor. More specifically, the project focuses on a thorough description of the safety and security systems that govern the operation of an EPR reactor and its plant. The process consisted on classify and summarize the different operating systems of this nuclear plant, studying its characteristics and operating parameters. We have also studied the most common accidents that can occur in this type of nuclear power plants. After the analysis and study on the EPR reactor, it can be concluded that nuclear power plants operating with this type of reactor undergo a series of improvements in the prevention of accidents, as well as a number of design improvements in several reactor systems and components, such as the vessel, the SG, etc.

Diseño y evaluación de un procedimiento on-line para la biorremediación de aguas radiactivas en centrales nucleares

Recientemente se ha demostrado la existencia de microorganismos en las piscinas de almacenamiento de combustible nuclear gastado en las centrales nucleares utilizando técnicas convencionales de cultivo en el laboratorio. Estudios posteriores han puesto de manifiesto que los microorganismos presentes eran capaces de colonizar las paredes de acero inoxidable de las piscinas formando biopelículas. Adicionalmente se ha observado la capacidad de estas biopelículas de retener radionúclidos, lo que hace pensar en la posibilidad de utilizarlas en la descontaminación de las aguas radiactivas de las piscinas. En la presente tesis se plantea conocer más profundamente la biodiversidad microbiana de las biopelículas utilizando técnicas de biología molecular como la clonación, además de desarrollar un sistema de descontaminación a escala piloto con el objetivo de valorar si el proceso podría resultar escalable a nivel industrial. Para ello se diseñaron y fabricaron dos biorreactores en acero inoxidable compatibles con las condiciones específicas de seguridad sísmica y protección frente a la radiación en la zona controlada de una central nuclear. Los biorreactores se instalaron en la Central Nuclear de Cofrentes (Valencia) en las proximidades de las piscinas de almacenamiento de combustible nuclear gastado y precediendo a las resinas de intercambio iónico, de forma que reciben el agua de las piscinas permitiendo el análisis in situ de la radiación eliminada del agua de las mismas. Se conectó una lámpara de luz ultravioleta a uno de los biorreactores para poder comparar el desarrollo de bipelículas y la retención de radiactividad en ambas condiciones. En estos biorreactores se introdujeron ovillos de acero inoxidable y de titanio que se extrajeron a diversos tiempos, hasta 635 días para los ovillos de acero inoxidable y hasta 309 días para los ovillos de titanio. Se analizaron las biopelículas desarrolladas sobre los ovillos por microscopía electrónica de barrido y por microscopía de epifluorescencia. Se extrajo el ADN de las biopelículas y, tras su clonación, se identificaron los microorganismos por técnicas independientes de cultivo. Asimismo se determinó por espectrometría gamma la capacidad de las biopelículas para retener radionúclidos. Los microorganismos radiorresistentes identificados pertenecen a los grupos filogenéticos Alpha-proteobacteria, Gamma-proteobacteria, Actinobacteria, Deinococcus-Thermus y Bacteroidetes. Las secuencias de estos microorganismos se han depositado en el GenBank con los números de acceso KR817260-KR817405. Se ha observado una distribución porcentual ligeramente diferente en relación con el tipo de biorreactor. Las biopelículas han retenido fundamentalmente radionúclidos de activación. La suma de Co-60 y Mn-54 ha llegado en ocasiones al 97%. Otros radionúclidos retenidos han sido Cr-51, Co-58, Fe-59, Zn-65 y Zr-95. Se sugiere un mecanismo del proceso de retención de radionúclidos relacionado con el tiempo de formación y desaparición de las biopelículas. Se ha valorado que el proceso escalable puede ser económicamente rentable. ABSTRACT The existence of microorganisms in spent nuclear fuel pools has been demonstrated recently in nuclear power plants by using conventional microbial techniques. Subsequent studies have revealed that those microorganisms were able to colonize the stainless steel pool walls forming biofilms. Additionally, it has been observed the ability of these biofilms to retain radionuclides, which suggests the possibility of using them for radioactive water decontamination purposes. This thesis presents deeper knowledge of microbial biofilms biodiversity by using molecular biology techniques such as cloning, and develops a decontamination system on a pilot scale, in order to assess whether the process could be scalable to an industrial level. Aiming to demonstrate this was feasible, two stainless steel bioreactors were designed and manufactured, both were compatible with seismic and radiation protection standards in the controlled zone of a nuclear plant. These bioreactors were installed in the Cofrentes Nuclear Power Plant (Valencia) next to the spent nuclear fuel pools and preceding (upstream) ion exchange resins. This configuration allowed the bioreactors to receive water directly from the pools allowing in situ analysis of radiation removal. One ultraviolet lamp was connected to one of the bioreactors to compare biofilms development and radioactivity retention in both conditions. Stainless steel and titanium balls were introduced into these bioreactors and were removed after different time periods, up to 635 days for stainless steel balls and up to 309 days for titanium. Biofilms developed on the balls were analyzed by scanning electron microscopy and epifluorescence microscopy. DNA was extracted from the biofilms, was cloned and then the microorganisms were identified by independent culture techniques. Biofilms ability to retain radionuclides was also determined by gamma spectrometry. The identified radioresistant organisms belong to the phylogenetic groups Alphaproteobacteria, Gamma-proteobacteria, Actinobacteria, Deinococcus-Thermus and Bacteroidetes. The sequences of these microorganisms have been deposited in GenBank (access numbers KR817260-KR817405). A different distribution of microorganisms was observed in relation to the type of bioreactor. Biofilms have essentially retained activation radionuclides. Sometimes the sum of Co-60 and Mn-54 reached 97%. Cr-51, Co-58, Fe-59, Zn-65 and Zr-95 have also been retained. A radionuclide retention process mechanism related to biofilms formation and disappearance time is suggested. It has been assessed that the scalable process can be economically profitable.

Fukushima: rescate urbano

This report explains both in Portuguese and Spanish the situation of the province of Fukushima in Japan after the accident of the Dai-Ichi nuclear power plant and the following reconstruction around this area by architects like Shigeru Ban, Toyo Ito, Kazuyo Sejima or Riken Yamamoto. This report also analyzes the role of the architect as a mediator in between the people of the northern coast and the japanese government which was extraordinary important in the first stages of the reconstruction after the earthquake. Este artículo describe tanto en Castellano como en Portugués la situación de la prefectura de Fukushima al norte de Japón tras el letal accidente de la central nuclear de Dai-Ichi. En él se detalla la reconstrucción en torno a esta zona por parte de arquitectos como Shigeru Ban, Toyo Ito, Riken Yamamoto o Kazuyo Sejima. También se estudia el rol del arquitecto como mediador entre el gobierno y los habitantes de la costa norte de Japón que fue decisivo en los meses posteriores al desastre.

Synthetic zeolites and other microporous oxide molecular sieves

Use of synthetic zeolites and other microporous oxides since 1950 has improved insulated windows, automobile air-conditioning, refrigerators, air brakes on trucks, laundry detergents, etc. Their large internal pore volumes, molecular-size pores, regularity of crystal structures, and the diverse framework chemical compositions allow “tailoring” of structure and properties. Thus, highly active and selective catalysts as well as adsorbents and ion exchangers with high capacities and selectivities were developed. In the petroleum refining and petrochemical industries, zeolites have made possible cheaper and lead-free gasoline, higher performance and lower-cost synthetic fibers and plastics, and many improvements in process efficiency and quality and in performance. Zeolites also help protect the environment by improving energy efficiency, reducing automobile exhaust and other emissions, cleaning up hazardous wastes (including the Three Mile Island nuclear power plant and other radioactive wastes), and, as specially tailored desiccants, facilitating the substitution of new refrigerants for the ozone-depleting chlorofluorocarbons banned by the Montreal Protocol.

PCRELAP5 - Programa de cálculo para os dados de entrada do código RELAP5

Após os acidentes nucleares ocorridos no mundo, critérios e requisitos extremamente rígidos para a operação das instalações nucleares foram determinados pelos órgãos internacionais que regulam essas instalações. A partir da ocorrência destes eventos, as operadoras de plantas nucleares necessitam simular alguns acidentes e transientes, por meio de programas computacionais específicos, para obter a licença de operação de uma planta nuclear. Com base neste cenário, algumas ferramentas computacionais sofisticadas têm sido utilizadas como o Reactor Excursion and Leak Analysis Program (RELAP5), que é o código mais utilizado para a análise de acidentes e transientes termo-hidráulicos em reatores nucleares no Brasil e no mundo. Uma das maiores dificuldades na simulação usando o código RELAP5 é a quantidade de informações geométricas da planta necessárias para a análise de acidentes e transientes termo-hidráulicos. Para a preparação de seus dados de entrada é necessário um grande número de operações matemáticas para calcular a geometria dos componentes. Assim, a fim de realizar estes cálculos e preparar dados de entrada para o RELAP5, um pré-processador matemático amigável foi desenvolvido, neste trabalho. O Visual Basic for Applications (VBA), combinado com o Microsoft Excel, foi utilizado e demonstrou ser um instrumento eficiente para executar uma série de tarefas no desenvolvimento desse pré-processador. A fim de atender as necessidades dos usuários do RELAP5, foi desenvolvido o Programa de Cálculo do RELAP5 PCRELAP5 onde foram codificados todos os componentes que constituem o código, neste caso, todos os cartões de entrada inclusive os opcionais de cada um deles foram programados. Adicionalmente, uma versão em inglês foi criada para PCRELAP5. Também um design amigável do PCRELAP5 foi desenvolvido com a finalidade de minimizar o tempo de preparação dos dados de entrada e diminuir os erros cometidos pelos usuários do código RELAP5. Nesse trabalho, a versão final desse pré-processador foi aplicada com sucesso para o Sistema de Injeção de Emergência (SIE) da usina Angra 2.

Aplicação de mapas auto-organizáveis na classificação de padrões de escoamento bifásico

O escoamento bifásico de gás-líquido é encontrado em muitos circuitos fechados que utilizam circulação natural para fins de resfriamento. O fenômeno da circulação natural é importante nos recentes projetos de centrais nucleares para a remoção de calor. O circuito de circulação natural (Circuito de Circulação Natural - CCN), instalado no Instituto de Pesquisas Energéticas e Nucleares, IPEN / CNEN, é um circuito experimento concebido para fornecer dados termo-hidráulicos relacionados com escoamento monofásico ou bifásico em condições de circulação natural. A estimativa de transferência de calor tem sido melhorada com base em modelos que requerem uma previsão precisa de transições de padrão de escoamento. Este trabalho apresenta testes experimentais desenvolvidos no CCN para a visualização dos fenômenos de instabilidade em ciclos de circulação natural básica e classificar os padrões de escoamento bifásico associados aos transientes e instabilidades estáticas de escoamento. As imagens são comparadas e agrupadas utilizando mapas auto-organizáveis de Kohonen (SOM), aplicados em diferentes características da imagem digital. Coeficientes da Transformada Discreta de Cossenos de Quadro Completo (FFDCT) foram utilizados como entrada para a tarefa de classificação, levando a bons resultados. Os protótipos de FFDCT obtidos podem ser associados a cada padrão de escoamento possibilitando uma melhor compreensão da instabilidade observada. Uma metodologia sistemática foi utilizada para verificar a robustez do método.

Bulgarian-Russian games in the energy sector: an outcome is getting closer. OSW Commentary No. 61, 2011-10-5

Bulgaria and Russia are entering the final phase of setting the conditions of their co-operation in the energy sector. A new gas contract is being negotiated because the currently applicable agreements will have expired by the end of 2012. The fate of two major energy projects – whose implementation depends on good co-operation between Sofia and Moscow: the Burgas– –Alexandroupolis oil pipeline and the construction of a Bulgarian nuclear power plant in Belene with Russian participation – is currently being decided. Another issue ever-present on the agenda is the future of the South Stream gas pipeline promoted by Russia, which is to run through Bulgarian territory. The outcome of all the aforementioned discussions and negotiations will determine for years the model of Bulgarian-Russian relations and may strongly affect the shape of the oil, gas and electricity markets in South-Eastern Europe.

The shadow of Chornobyl. Ukraine thirty years after the disaster. OSW COMMENTARY NUMBER 210/22.04.2016

Thirty years after the Chornobyl nuclear power plant disaster, its aftermath and consequences are still a permanent element of the economic, environmental and social situation of Ukraine, Belarus and some regions of Russia. Ukraine, to which the scope of this text is limited, experienced the most severe shock because, among other factors, the plant where the accident took place was located just 100 km away from Kyiv. Its consequences have affected the course of political developments in the country, and have become part of the newly-shaped national identity of independent Ukraine. The country bore the huge cost of the clean-up effort but did not give up on nuclear energy, and today nuclear power plants generate more than half of its electricity. The system of social benefits for people recognised as disaster survivors, which was put in place by the Soviet government, has become a huge burden on the country’s budget; if implemented fully, it would account for more than 10% of total public spending, and is therefore being implemented to only a partial extent. This system has reinforced the Ukrainian people’s sense of helplessness and dependence on the state. The disaster has also become part of the ‘victim nation’ blueprint of the Ukrainian national myth, which it has further solidified. The technological and environmental consequences of the disaster, and hence also its economic costs, will persist for centuries, while the social consequences will dissipate as the affected generation passes away. In any case, Chornobyl will remain an important part of the life of the Ukrainian state and society.

NRC plan for cleanup operations at Three Mile Island Unit 2 /

"NUREG-0698."

Optimization of pipeline transport for CO2 sequestration

Coal fired power generation will continue to provide energy to the world for the foreseeable future. However, this energy use is a significant contributor to increased atmospheric CO2 concentration and, hence, global warming. Capture and disposal Of CO2 has received increased R&D attention in the last decade as the technology promises to be the most cost effective for large scale reductions in CO2 emissions. This paper addresses CO2 transport via pipeline from capture site to disposal site, in terms of system optimization, energy efficiency and overall economics. Technically, CO2 can be transported through pipelines in the form of a gas, a supercritical. fluid or in the subcooled liquid state. Operationally, most CO2 pipelines used for enhanced oil recovery transport CO2 as a supercritical fluid. In this paper, supercritical fluid and subcooled liquid transport are examined and compared, including their impacts on energy efficiency and cost. Using a commercially available process simulator, ASPEN PLUS 10.1, the results show that subcooled liquid transport maximizes the energy efficiency and minimizes the Cost Of CO2 transport over long distances under both isothermal and adiabatic conditions. Pipeline transport of subcooled liquid CO2 can be ideally used in areas of cold climate or by burying and insulating the pipeline. In very warm climates, periodic refrigeration to cool the CO2 below its critical point of 31.1 degrees C, may prove economical. Simulations have been used to determine the maximum safe pipeline distances to subsequent booster stations as a function of inlet pressure, environmental temperature and ground level heat flux conditions. (c) 2005 Published by Elsevier Ltd.

Fibre agglomerate transport in a horizontal flow

An experimental and theoretical study of the transport of mineral wool fibre agglomerates in nuclear power plant containment sumps is being performed. A racetrack channel was devised to provide data for the validation of numerical models, which are intended to model the transport of fibre agglomerates. The racetrack channel provides near uniform and steady conditions that lead to either the sedimentation or suspension of the agglomerates. Various experimental techniques were used to determine the velocity conditions and the distribution of the fibre agglomerates in the channel. The fibre agglomerates are modelled as fluid particles in the Eulerian reference frame. Simulations of pure sedimentation of a known mass and volume of agglomerations show that the transport of the fibre agglomerates can be replicated. The suspension of the fibres is also replicated in the simulations; however, the definition of the fibre agglomerate phase is strongly dependent on the selected density and diameter. Detailed information on the morphology of the fibre agglomerates is lacking for the suspension conditions, as the fibre agglomerates may undergo breakage and erosion. Therefore, ongoing work, which is described here, is being pursued to improve the experimental characterisation of the suspended transport of the fibre agglomerates.

The role of nuclear and other conventional power plants in the flexible energy system

This thesis reviews the role of nuclear and conventional power plants in the future energy system. The review is done by utilizing freely accesible publications in addition to generating load duration and ramping curves for Nordic energy system. As the aim of the future energy system is to reduce GHG-emissions and avoid further global warming, the need for flexible power generation increases with the increased share of intermittent renewables. The goal of this thesis is to offer extensive understanding of possibilities and restrictions that nuclear power and conventional power plants have regarding flexible and sustainable generation. As a conclusion, nuclear power is the only technology that is able to provide large scale GHG-free power output variations with good ramping values. Most of the currently operating plants are able to take part in load following as the requirement to do so is already required to be included in the plant design. Load duration and ramping curves produced prove that nuclear power is able to cover most of the annual generation variation and ramping needs in the Nordic energy system. From the conventional power generation methods, only biomass combustion can be considered GHG-free because biomass is considered carbon neutral. CFB combusted biomass has good load follow capabilities in good ramping and turndown ratios. All the other conventional power generation technologies generate GHG-emissions and therefore the use of these technologies should be reduced.

Phipps Bend Nuclear Plant socioeconomic monitoring report.

"PBNP-SMR-9, December 31, 1981."

Phipps Bend Nuclear Plant socioeconomic monitoring and mitigation report.

"PBNP-SMR-10, September 30, 1982. SP895."