Uncertainty methods inactivation and inventory calculations

For a number of important nuclides, complete activation data libraries with covariance data will be produced, so that uncertainty propagation in fuel cycle codes (in this case ACAB,FISPIN, ...) can be developed and tested. Eventually, fuel inventory codes should be able to handle the complete set of uncertainty data, i.e. those of nuclear reactions (cross sections, etc.), radioactive decay and fission yield data. For this, capabilities will be developed both to produce covariance data and to propagate the uncertainties through the inventory calculations.

Application of noise analysis for sensor surveillance in Trillo NPP

It is a known fact that noise analysis is a suitable method for sensor performance surveillance. In particular, controlling the response time of a sensor is an efficient way to anticipate failures and to have the opportunity to prevent them. In this work the response times of several sensors of Trillo NPP are estimated by means of noise analysis. The procedure applied consists of modeling each sensor with autoregressive methods and getting the searched parameter by analyzing the response of the model when a ramp is simulated as the input signal. Core exit thermocouples and in core self-powered neutron detectors are the main sensors analyzed but other plant sensors are studied as well. Since several measurement campaigns have been carried out, it has been also possible to analyze the evolution of the estimated parameters during more than one fuel cycle. Some sensitivity studies for the sample frequency of the signals and its influence on the response time are also included. Calculations and analysis have been done in the frame of a collaboration agreement between Trillo NPP operator (CNAT) and the School of Mines of Madrid.

MANDRÁGORAS: MITOS E ASPECTOS DA CULTURA DE ISRAEL A PARTIR DE GÊNESIS 25 A 36

A sexualidade de Lea e Raquel, o útero, as mandrágoras e o corpo de Jacó são fatores que definem o alicerce do nosso texto como espaços de diálogo, mediação e estrutura do cenário. O destaque principal está sob o capítulo 30.14-16 que retrata a memória das mandrágoras. Como plantas místicas elas dominam o campo religioso e como plantas medicinais elas são utilizadas para solucionar problemas biológicos. As instituições e sociedades detentoras de uma ideologia e de leis que regulamentam uma existência apresentam na narrativa, duas irmãs, mas também esposas de um mesmo homem que, manipuladas por essa instituição que minimiza e oprime a mulher, principalmente a estéril, confina-as como simples objeto de sexualidade e mantenedoras da descendência por meio da maternidade. A memória das mandrágoras é sinal de que a prática existente circundava uma religião não monoteísta. Ela existia sociologicamente por meio de sincretismos, força e poderes sócio-culturais e religiosos. Era constituída das memórias de mulheres que manipulavam e dominavam o poder sagrado para controle de suas necessidades. O discurso dessas mulheres, em nossa unidade, prova que o discurso dessa narrativa não se encontra somente no plano individual, mas também se estende a nível comunitário, espaço que as define e lhes concede importância por meio do casamento e dádivas da maternidade como continuidade da descendência. São mulheres que dominaram um espaço na história com suas lutas e vitórias, com atos de amor e de sofrimento, de crenças e poderes numa experiência religiosa dominada pelo masculino que vai além do nosso conhecimento atual. As lutas firmadas na fé e na ideologia dessas mulheres definiram e acentuaram seu papel de protagonistas nas narrativas 9 bíblicas que estudamos no Gênesis. A conservação dessas narrativas, e do espaço teológico da época, definiu espaços, vidas, gerações e tribos que determinaram as gerações prometidas e fecharam um ciclo: o da promessa de Iahweh quanto à descendência desde Abraão. Os mitos e as crenças foram extintos para dar espaço a uma fé monoteísta, mas a experiência religiosa

Essential role of germinal vesicle material in the meiotic cell cycle of Xenopus oocytes

In almost all animal species, immature oocytes are arrested naturally in the first meiotic prophase, with a large nucleus called the germinal vesicle. A number of previous studies showed that both activation of maturation/M phase-promoting factor (MPF) (assayed by semiquantitative cytological methods) and some other maturational events occur essentially normally in enucleated oocytes from many amphibian species and mice. Hence, for nearly three decades, it has generally been believed that nuclear material is dispensable for MPF activation and the meiotic cell cycle in vertebrate oocytes. Here, we have challenged this view by examining the histone H1 kinase activities and the molecular forms of MPF in experimentally manipulated Xenopus oocytes. We show that oocytes injected with nuclear material undergo much more rapid MPF activation and maturation than uninjected control oocytes. Conversely, enucleated oocytes, unlike nucleated counterparts, undergo only weak MPF activation in meiosis I and no detectable MPF reactivation in meiosis II, the latter accompanying inhibitory tyrosine phosphorylation of cdc2 kinase, the catalytic subunit of MPF. These results argue strongly that nuclear material is indispensable for the meiotic cell cycle, particularly MPF reactivation (or cdc2 tyrosine dephosphorylation) on entry into meiosis II, in Xenopus oocytes. The classical and general view may thus need reconsideration.

Structural protein 4.1 is located in mammalian centrosomes

Structural protein 4.1 was first characterized as an important 80-kDa protein in the mature red cell membrane skeleton. It is now known to be a member of a family of protein isoforms detected at diverse intracellular sites in many nucleated mammalian cells. We recently reported that protein 4.1 isoforms are present at interphase in nuclear matrix and are rearranged during the cell cycle. Here we report that protein 4.1 epitopes are present in centrosomes of human and murine cells and are detected by using affinity-purified antibodies specific for 80-kDa red cell 4.1 and for 4.1 peptides. Immunofluorescence, by both conventional and confocal microscopy, showed that protein 4.1 epitopes localized in the pericentriolar region. Protein 4.1 epitopes remained in centrosomes after extraction of cells with detergent, salt, and DNase. Higher resolution electron microscopy of detergent-extracted cell whole mounts showed centrosomal protein 4.1 epitopes distributed along centriolar cylinders and on pericentriolar fibers, at least some of which constitute the filamentous network surrounding each centriole. Double-label electron microscopy showed that protein 4.1 epitopes were predominately localized in regions also occupied by epitopes for centrosome-specific autoimmune serum 5051 but were not found on microtubules. Our results suggest that protein 4.1 is an integral component of centrosome structure, in which it may play an important role in centrosome function during cell division and organization of cellular architecture.

Scoping assessment of the environmental health risk associated with accidents in the LWR supporting fuel cycle /

Issued Feb. 1977.

Criteria for selection of fuel cycle and major materials licenses needing radiological contingency plans /

"NUREG-0767."

MANDRÁGORAS: MITOS E ASPECTOS DA CULTURA DE ISRAEL A PARTIR DE GÊNESIS 25 A 36

A sexualidade de Lea e Raquel, o útero, as mandrágoras e o corpo de Jacó são fatores que definem o alicerce do nosso texto como espaços de diálogo, mediação e estrutura do cenário. O destaque principal está sob o capítulo 30.14-16 que retrata a memória das mandrágoras. Como plantas místicas elas dominam o campo religioso e como plantas medicinais elas são utilizadas para solucionar problemas biológicos. As instituições e sociedades detentoras de uma ideologia e de leis que regulamentam uma existência apresentam na narrativa, duas irmãs, mas também esposas de um mesmo homem que, manipuladas por essa instituição que minimiza e oprime a mulher, principalmente a estéril, confina-as como simples objeto de sexualidade e mantenedoras da descendência por meio da maternidade.A memória das mandrágoras é sinal de que a prática existente circundava uma religião não monoteísta. Ela existia sociologicamente por meio de sincretismos, força e poderes sócio-culturais e religiosos. Era constituída das memórias de mulheres que manipulavam e dominavam o poder sagrado para controle de suas necessidades. O discurso dessas mulheres, em nossa unidade, prova que o discurso dessa narrativa não se encontra somente no plano individual, mas também se estende a nível comunitário, espaço que as define e lhes concede importância por meio do casamento e dádivas da maternidade como continuidade da descendência. São mulheres que dominaram um espaço na história com suas lutas e vitórias, com atos de amor e de sofrimento, de crenças e poderes numa experiência religiosa dominada pelo masculino que vai além do nosso conhecimento atual. As lutas firmadas na fé e na ideologia dessas mulheres definiram e acentuaram seu papel de protagonistas nas narrativas 9 bíblicas que estudamos no Gênesis. A conservação dessas narrativas, e do espaço teológico da época, definiu espaços, vidas, gerações e tribos que determinaram as gerações prometidas e fecharam um ciclo: o da promessa de Iahweh quanto à descendência desde Abraão. Os mitos e as crenças foram extintos para dar espaço a uma fé monoteísta, mas a experiência religiosa dessas mulheres definiu um espaço: do poder sagrado e místico que corroborava com suas necessidades e definiam sua teologia.(AU)

Performance, emission and combustion characteristics of an indirect injection (IDI) multi-cylinder compression ignition (CI) engine operating on neat jatropha and karanj oils preheated by jacket water

Renewable non-edible plant oils such as jatropha and karanj have potential to substitute fossil diesel fuels in CI engines. A multi-cylinder water cooled IDI type CI engine has been tested with jatropha and karanj oils and comparisons made against fossil diesel. The physical and chemical properties of the three fuels were measured to investigate the suitability of jatropha and karanj oils as fuels for CI engines. The engine cooling water circuit and fuel supply systems were modified such that hot jacket water preheated the neat plant oil prior to injection. Between jatropha and karanj there was little difference in the performance, emission and combustion results. Compared to fossil diesel, the brake specific fuel consumption on volume basis was around 3% higher for the plant oils and the brake thermal efficiency was almost similar. Jatropha and karanj operation resulted in higher CO 2 and NO x emissions by 7% and 8% respectively, as compared to diesel. The cylinder gas pressure diagram showed stable engine operation with both plant oils. At full load, the plant oils gave around 3% higher peak cylinder pressure than fossil diesel. With the plant oils, cumulative heat release was smaller at low load and almost similar at full load, compared to diesel. At full load, the plant oils exhibited 5% shorter combustion duration. The study concludes that the IDI type CI engine can be efficiently operated with neat jatropha (or karanj) oil preheated by jacket water, after small modifications of the engine cooling and fuel supply circuits. © 2012 Elsevier Ltd.

Defining the Role of Host Cell Chromatin Traps in Chlamydia trachomatis Pathogenesis

Chlamydia trachomatis (CT) is the most common bacterial agent of sexually transmitted infection and can cause damaging inflammation of the female reproductive tract. As an obligate intracellular pathogen, CT must exit exhausted host cells in a manner that favors successful dissemination. Epithelial cells infected with CT expel decondensed nuclear chromatin at the conclusion of an infectious cycle, and these ensnare CT particles. Whether these chromatin traps benefit the host or the pathogen is not obvious. The overall goal of this work is to begin discerning between these possibilities by determining how chromatin traps impact CT survival following exit and how traps contribute to CT-induced inflammatory processes.

Core physics and safety analysis of Generation-IV Sodium Fast Reactors using existing and newly developed computational tools

El futuro de la energía nuclear de fisión dependerá, entre otros factores, de la capacidad que las nuevas tecnologías demuestren para solventar los principales retos a largo plazo que se plantean. Los principales retos se pueden resumir en los siguientes aspectos: la capacidad de proporcionar una solución final, segura y fiable a los residuos radiactivos; así como dar solución a la limitación de recursos naturales necesarios para alimentar los reactores nucleares; y por último, una mejora robusta en la seguridad de las centrales que en definitiva evite cualquier daño potencial tanto en la población como en el medio ambiente como consecuencia de cualquier escenario imaginable o más allá de lo imaginable. Siguiendo estas motivaciones, la Generación IV de reactores nucleares surge con el compromiso de proporcionar electricidad de forma sostenible, segura, económica y evitando la proliferación de material fisible. Entre los sistemas conceptuales que se consideran para la Gen IV, los reactores rápidos destacan por su capacidad potencial de transmutar actínidos a la vez que permiten una utilización óptima de los recursos naturales. Entre los refrigerantes que se plantean, el sodio parece una de las soluciones más prometedoras. Como consecuencia, esta tesis surgió dentro del marco del proyecto europeo CP-ESFR con el principal objetivo de evaluar la física de núcleo y seguridad de los reactores rápidos refrigerados por sodio, al tiempo que se desarrollaron herramientas apropiadas para dichos análisis. Efectivamente, en una primera parte de la tesis, se abarca el estudio de la física del núcleo de un reactor rápido representativo, incluyendo el análisis detallado de la capacidad de transmutar actínidos minoritarios. Como resultado de dichos análisis, se publicó un artículo en la revista Annals of Nuclear Energy [96]. Por otra parte, a través de un análisis de un hipotético escenario nuclear español, se evalúo la disponibilidad de recursos naturales necesarios en el caso particular de España para alimentar una flota específica de reactores rápidos, siguiendo varios escenarios de demanda, y teniendo en cuenta la capacidad de reproducción de plutonio que tienen estos sistemas. Como resultado de este trabajo también surgió una publicación en otra revista científica de prestigio internacional como es Energy Conversion and Management [97]. Con objeto de realizar esos y otros análisis, se desarrollaron diversos modelos del núcleo del ESFR siguiendo varias configuraciones, y para diferentes códigos. Por otro lado, con objeto de poder realizar análisis de seguridad de reactores rápidos, son necesarias herramientas multidimensionales de alta fidelidad específicas para reactores rápidos. Dichas herramientas deben integrar fenómenos relacionados con la neutrónica y con la termo-hidráulica, entre otros, mediante una aproximación multi-física. Siguiendo este objetivo, se evalúo el código de difusión neutrónica ANDES para su aplicación a reactores rápidos. ANDES es un código de resolución nodal que se encuentra implementado dentro del sistema COBAYA3 y está basado en el método ACMFD. Por lo tanto, el método ACMFD fue sometido a una revisión en profundidad para evaluar su aptitud para la aplicación a reactores rápidos. Durante ese proceso, se identificaron determinadas limitaciones que se discutirán a lo largo de este trabajo, junto con los desarrollos que se han elaborado e implementado para la resolución de dichas dificultades. Por otra parte, se desarrolló satisfactoriamente el acomplamiento del código neutrónico ANDES con un código termo-hidráulico de subcanales llamado SUBCHANFLOW, desarrollado recientemente en el KIT. Como conclusión de esta parte, todos los desarrollos implementados son evaluados y verificados. En paralelo con esos desarrollos, se calcularon para el núcleo del ESFR las secciones eficaces en multigrupos homogeneizadas a nivel nodal, así como otros parámetros neutrónicos, mediante los códigos ERANOS, primero, y SERPENT, después. Dichos parámetros se utilizaron más adelante para realizar cálculos estacionarios con ANDES. Además, como consecuencia de la contribución de la UPM al paquete de seguridad del proyecto CP-ESFR, se calcularon mediante el código SERPENT los parámetros de cinética puntual que se necesitan introducir en los típicos códigos termo-hidráulicos de planta, para estudios de seguridad. En concreto, dichos parámetros sirvieron para el análisis del impacto que tienen los actínidos minoritarios en el comportamiento de transitorios. Concluyendo, la tesis presenta una aproximación sistemática y multidisciplinar aplicada al análisis de seguridad y comportamiento neutrónico de los reactores rápidos de sodio de la Gen-IV, usando herramientas de cálculo existentes y recién desarrolladas ad' hoc para tal aplicación. Se ha empleado una cantidad importante de tiempo en identificar limitaciones de los métodos nodales analíticos en su aplicación en multigrupos a reactores rápidos, y se proponen interesantes soluciones para abordarlas. ABSTRACT The future of nuclear reactors will depend, among other aspects, on the capability to solve the long-term challenges linked to this technology. These are the capability to provide a definite, safe and reliable solution to the nuclear wastes; the limitation of natural resources, needed to fuel the reactors; and last but not least, the improved safety, which would avoid any potential damage on the public and or environment as a consequence of any imaginable and beyond imaginable circumstance. Following these motivations, the IV Generation of nuclear reactors arises, with the aim to provide sustainable, safe, economic and proliferationresistant electricity. Among the systems considered for the Gen IV, fast reactors have a representative role thanks to their potential capacity to transmute actinides together with the optimal usage of natural resources, being the sodium fast reactors the most promising concept. As a consequence, this thesis was born in the framework of the CP-ESFR project with the generic aim of evaluating the core physics and safety of sodium fast reactors, as well as the development of the approppriated tools to perform such analyses. Indeed, in a first part of this thesis work, the main core physics of the representative sodium fast reactor are assessed, including a detailed analysis of the capability to transmute minor actinides. A part of the results obtained have been published in Annals of Nuclear Energy [96]. Moreover, by means of the analysis of a hypothetical Spanish nuclear scenario, the availability of natural resources required to deploy an specific fleet of fast reactor is assessed, taking into account the breeding properties of such systems. This work also led to a publication in Energy Conversion and Management [97]. In order to perform those and other analyses, several models of the ESFR core were created for different codes. On the other hand, in order to perform safety studies of sodium fast reactors, high fidelity multidimensional analysis tools for sodium fast reactors are required. Such tools should integrate neutronic and thermal-hydraulic phenomena in a multi-physics approach. Following this motivation, the neutron diffusion code ANDES is assessed for sodium fast reactor applications. ANDES is the nodal solver implemented inside the multigroup pin-by-pin diffusion COBAYA3 code, and is based on the analytical method ACMFD. Thus, the ACMFD was verified for SFR applications and while doing so, some limitations were encountered, which are discussed through this work. In order to solve those, some new developments are proposed and implemented in ANDES. Moreover, the code was satisfactorily coupled with the thermal-hydraulic code SUBCHANFLOW, recently developed at KIT. Finally, the different implementations are verified. In addition to those developments, the node homogenized multigroup cross sections and other neutron parameters were obtained for the ESFR core using ERANOS and SERPENT codes, and employed afterwards by ANDES to perform steady state calculations. Moreover, as a result of the UPM contribution to the safety package of the CP-ESFR project, the point kinetic parameters required by the typical plant thermal-hydraulic codes were computed for the ESFR core using SERPENT, which final aim was the assessment of the impact of minor actinides in transient behaviour. All in all, the thesis provides a systematic and multi-purpose approach applied to the assessment of safety and performance parameters of Generation-IV SFR, using existing and newly developed analytical tools. An important amount of time was employed in identifying the limitations that the analytical nodal diffusion methods present when applied to fast reactors following a multigroup approach, and interesting solutions are proposed in order to overcome them.

Nuclear Data Uncertainty Propagation to Reactivity Coefficients of a Sodium Fast Reactor

The assessment of the uncertainty levels on the design and safety parameters for the innovative European Sodium Fast Reactor (ESFR) is mandatory. Some of these relevant safety quantities are the Doppler and void reactivity coefficients, whose uncertainties are quantified. Besides, the nuclear reaction data where an improvement will certainly benefit the design accuracy are identified. This work has been performed with the SCALE 6.1 codes suite and its multigroups cross sections library based on ENDF/B-VII.0 evaluation.

A comparative study of Monte Carlo-coupled depletion codes applied to a Sodium Fast Reactor design loaded with minor actinides

inor actinides (MAs) transmutation is a main design objective of advanced nuclear systems such as generation IV Sodium Fast Reactors (SFRs). In advanced fuel cycles, MA contents in final high level waste packages are main contributors to short term heat production as well as to long-term radiotoxicity. Therefore, MA transmutation would have an impact on repository designs and would reduce the environment burden of nuclear energy. In order to predict such consequences Monte Carlo (MC) transport codes are used in reactor design tasks and they are important complements and references for routinely used deterministic computational tools. In this paper two promising Monte Carlo transport-coupled depletion codes, EVOLCODE and SERPENT, are used to examine the impact of MA burning strategies in a SFR core, 3600 MWth. The core concept proposal for MA loading in two configurations is the result of an optimization effort upon a preliminary reference design to reduce the reactivity insertion as a consequence of sodium voiding, one of the main concerns of this technology. The objective of this paper is double. Firstly, efficiencies of the two core configurations for MA transmutation are addressed and evaluated in terms of actinides mass changes and reactivity coefficients. Results are compared with those without MA loading. Secondly, a comparison of the two codes is provided. The discrepancies in the results are quantified and discussed.