Literatura académica sobre el tema "Aster code"
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Artículos de revistas sobre el tema "Aster code"
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Arsic, Dusan, Ivana Ivanovic, Aleksandar Sedmak, Mirjana Lazic, Dragan Kalaba, Ivana Cekovic y Nada Ratkovic. "Experimental and numerical study of temperature field during hard facing of different carbon steels". Thermal Science 24, n.º 3 Part B (2020): 2233–41. http://dx.doi.org/10.2298/tsci190717338a.
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In this research the 3-D transient non-linear thermal analysis of the hard-facing process was performed by using the experimental testing and finite element method. Testing was done at three different carbon steels and the obtained results were compared to one obtained by empirical formulas and welding recommendations. Experimental testing was done on hard faced specimens (plates) with different thickness. Temperatures and temperature cycles was measured by using thermocouples in order to determine maximal temperature and cooling time between 800?C and 500?C. After experimental testing the finite element method analysis was done. The simulations were executed on the open source platform Salome using the open source finite element solver Code Aster. The Gaussian double ellipsoid was selected in order to enable greater possibilities for the calculation of the moving heat source. The numerical results were compared with available experimental and mathematical results.
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Maksimova, E. A., A. V. Cherednichenko y I. Yu Savelyeva. "Calculation of the problem of thermoplasticity on the example of a stationary power plant flange using free software Code Aster". Journal of Physics: Conference Series 1902, n.º 1 (1 de mayo de 2021): 012121. http://dx.doi.org/10.1088/1742-6596/1902/1/012121.
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Castriota, A., V. Dattoma y R. Nobile. "Comparison of fatigue damage criteria for a CFRP aeronautical joint subjected to random fatigue load". IOP Conference Series: Materials Science and Engineering 1214, n.º 1 (1 de enero de 2022): 012009. http://dx.doi.org/10.1088/1757-899x/1214/1/012009.
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Abstract The fatigue life prediction of components in CFRP subjected to random fatigue load was carried out considering different fatigue damage models. The selected component is a filled hole tension specimen, which is representative of the typical aeronautical riveted joint. The stress state of the riveted section was determined through a FEM model, created with CODE ASTER. Subsequently, the fatigue load history was introduced, calculating the stress field for the different load levels. Applying the constant life diagrams, fatigue cycles were counted and the damage was evaluated. Finally, the damage that occurs in the different ply of the specimen was calculated using different fatigue damage criteria present in literature. The creation of a parametric FEM model offers the possibility of optimizing the study and constitutes a useful tool in order to choose the most suitable damage criteria for the particular geometry and loading mode of the component. Moreover, different severity of the load history and different load sequence were introduced to show their effect in the fatigue failure.
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Taleb, L., S. Petit y J. F. Jullien. "Prediction of residual stresses in the heat affected zone". Journal de Physique IV 120 (diciembre de 2004): 705–12. http://dx.doi.org/10.1051/jp4:2004120081.
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In this paper the behavior of a disc made up of carbon manganese steel and subjected to an axisymmetric heating in its middle zone is considered. The applied thermal cycle generates localized metallurgical solid-solid phase transformations. Contrary to the study performed some years ago, the present work is concerned with relatively thick discs that lead to variable behavior according to axial direction. Experimentally, temperature and axial displacement of the face below have continuously been measured during tests. At the end of tests, the nature and the proportions of the final phases as well as residual stresses on both faces of the discs has also been assessed. These experimental results have been compared to numerical simulations using the finite element code ASTER, developed by Electricité de France (EDF), that enables to take into account the main mechanical consequences of phase transformations. From the obtained results it can be pointed out the significant importance to take into account the transformation induced plasticity (TRIP) phenomenon for better estimation of residual stresses.
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Md Ali, A., D. P. Solomatine y G. Di Baldassarre. "Assessing the impact of different sources of topographic data on 1-D hydraulic modelling of floods". Hydrology and Earth System Sciences Discussions 11, n.º 7 (3 de julio de 2014): 7375–408. http://dx.doi.org/10.5194/hessd-11-7375-2014.
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Abstract. Topographic data, such as digital elevation models (DEMs), are essential input in flood inundation modelling. DEMs can be derived from several sources either through remote sensing techniques (space-borne or air-borne imagery) or from traditional methods (ground survey). The Advanced Spaceborne Thermal Emission and Reflection Radiometer (ASTER), the Shuttle Radar Topography Mission (SRTM), the Light Detection and Ranging (LiDAR), and topographic contour maps are some of the most commonly used sources of data for DEMs. These DEMs are characterized by different precision and accuracy. On the one hand, the spatial resolution of low-cost DEMs from satellite imagery, such as ASTER and SRTM, is rather coarse (around 30–90 m). On the other hand, LiDAR technique is able to produce a high resolution DEMs (around 1m), but at a much higher cost. Lastly, contour mapping based on ground survey is time consuming, particularly for higher scales, and may not be possible for some remote areas. The use of these different sources of DEM obviously affects the results of flood inundation models. This paper shows and compares a number of hydraulic models developed using HEC-RAS as model code and the aforementioned sources of DEM as geometric input. The study was carried out on a reach of the Johor River, in Malaysia. The effect of the different sources of DEMs (and different resolutions) was investigated by considering the performance of the hydraulic models in simulating flood water levels as well as inundation maps. The outcomes of our study show that the use of different DEMs has serious implications to the results of hydraulic models. The outcomes also indicates the loss of model accuracy due to re-sampling the highest resolution DEM (i.e. LiDAR 1 m) to lower resolution are much less compared to the loss of model accuracy due to the use of low-cost DEM that have not only a lower resolution, but also a lower quality. Lastly, to better explore the sensitivity of the hydraulic models to different DEMs, we performed an uncertainty analysis based on the GLUE methodology.
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Szénási, Zoltán. "Materiality and Making Meaning". Hungarian Cultural Studies 16 (6 de septiembre de 2023): 109–22. http://dx.doi.org/10.5195/ahea.2023.497.
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In recent decades, scholars working in the realm of the metaphilology have focused increasingly on the materiality of texts; that is, the material aspect of texts in the making of meaning (cf. Jerome McGann’s “bibliographic code”). This article sets out by clarifying what we mean by the materiality of a text; it does so by outlining and discussing the ideas advanced by George Bornstein. Applying the methodology of historical bibliography, it then examines how the changing material context of the poem “Fortissimo,” by one of Hungary’s towering early twentieth-century literary figures, Mihály Babits, influenced that poem’s interpretability from the first stage of its existence to its multiple republications. This poem’s publication history is exceptional from several perspectives. The March 1, 1917, issue of the journal Nyugat was confiscated because of the poem, and its author was prosecuted for blasphemy. But the poem was published in French the same year, and in two anthologies in German the following year. “Fortissimo” became available in Hungarian again only after the Aster Revolution of 1918, in the volume A diadalmas forradalom könyve (The Book of the Triumphant Revolution), alongside works by many other authors, and, within days, once again in Nyugat. Szenasi.Zoltan@abtk.hu
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Md Ali, A., D. P. Solomatine y G. Di Baldassarre. "Assessing the impact of different sources of topographic data on 1-D hydraulic modelling of floods". Hydrology and Earth System Sciences 19, n.º 1 (30 de enero de 2015): 631–43. http://dx.doi.org/10.5194/hess-19-631-2015.
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Abstract. Topographic data, such as digital elevation models (DEMs), are essential input in flood inundation modelling. DEMs can be derived from several sources either through remote sensing techniques (spaceborne or airborne imagery) or from traditional methods (ground survey). The Advanced Spaceborne Thermal Emission and Reflection Radiometer (ASTER), the Shuttle Radar Topography Mission (SRTM), the light detection and ranging (lidar), and topographic contour maps are some of the most commonly used sources of data for DEMs. These DEMs are characterized by different precision and accuracy. On the one hand, the spatial resolution of low-cost DEMs from satellite imagery, such as ASTER and SRTM, is rather coarse (around 30 to 90 m). On the other hand, the lidar technique is able to produce high-resolution DEMs (at around 1 m), but at a much higher cost. Lastly, contour mapping based on ground survey is time consuming, particularly for higher scales, and may not be possible for some remote areas. The use of these different sources of DEM obviously affects the results of flood inundation models. This paper shows and compares a number of 1-D hydraulic models developed using HEC-RAS as model code and the aforementioned sources of DEM as geometric input. To test model selection, the outcomes of the 1-D models were also compared, in terms of flood water levels, to the results of 2-D models (LISFLOOD-FP). The study was carried out on a reach of the Johor River, in Malaysia. The effect of the different sources of DEMs (and different resolutions) was investigated by considering the performance of the hydraulic models in simulating flood water levels as well as inundation maps. The outcomes of our study show that the use of different DEMs has serious implications to the results of hydraulic models. The outcomes also indicate that the loss of model accuracy due to re-sampling the highest resolution DEM (i.e. lidar 1 m) to lower resolution is much less than the loss of model accuracy due to the use of low-cost DEM that have not only a lower resolution, but also a lower quality. Lastly, to better explore the sensitivity of the 1-D hydraulic models to different DEMs, we performed an uncertainty analysis based on the GLUE methodology.
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Rogic, Nikola, Annalisa Cappello y Fabrizio Ferrucci. "Role of Emissivity in Lava Flow ‘Distance-to-Run’ Estimates from Satellite-Based Volcano Monitoring". Remote Sensing 11, n.º 6 (19 de marzo de 2019): 662. http://dx.doi.org/10.3390/rs11060662.
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Remote sensing is an established technological solution for bridging critical gaps in volcanic hazard assessment and risk mitigation. The enormous amount of remote sensing data available today at a range of temporal and spatial resolutions can aid emergency management in volcanic crises by detecting and measuring high-temperature thermal anomalies and providing lava flow propagation forecasts. In such thermal estimates, an important role is played by emissivity—the efficiency with which a surface radiates its thermal energy at various wavelengths. Emissivity has a close relationship with land surface temperatures and radiant fluxes, and it impacts directly on the prediction of lava flow behavior, as mass flux estimates depend on measured radiant fluxes. Since emissivity is seldom measured and mostly assumed, we aimed to fill this gap in knowledge by carrying out a multi-stage experiment, combining laboratory-based Fourier transform infrared (FTIR) analyses, remote sensing data, and numerical modeling. We tested the capacity for reproducing emissivity from spaceborne observations using ASTER Global Emissivity Database (GED) while assessing the spatial heterogeneity of emissivity. Our laboratory-satellite emissivity values were used to establish a realistic land surface temperature from a high-resolution spaceborne payload (ETM+) to obtain an instant temperature–radiant flux and eruption rate results for the 2001 Mount Etna (Italy) eruption. Forward-modeling tests conducted on the 2001 ‘aa’ lava flow by means of the MAGFLOW Cellular Automata code produced differences of up to ~600 m in the simulated lava flow ‘distance-to-run’ for a range of emissivity values. Given the density and proximity of urban settlements on and around Mount Etna, these results may have significant implications for civil protection and urban planning applications.
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Bandini, G., S. Ederli, S. Perez-Martin, M. Haselbauer, W. Pfrang, L. E. Herranz, C. Berna et al. "ASTEC-Na code: Thermal-hydraulic model validation and benchmarking with other codes". Annals of Nuclear Energy 119 (septiembre de 2018): 427–39. http://dx.doi.org/10.1016/j.anucene.2017.12.016.
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Šadek, Siniša, Davor Grgić y Zdenko Šimić. "Application of ASTEC, MELCOR, and MAAP Computer Codes for Thermal Hydraulic Analysis of a PWR Containment Equipped with the PCFV and PAR Systems". Science and Technology of Nuclear Installations 2017 (2017): 1–16. http://dx.doi.org/10.1155/2017/8431934.
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The integrity of the containment will be challenged during a severe accident due to pressurization caused by the accumulation of steam and other gases and possible ignition of hydrogen and carbon monoxide. Installation of a passive filtered venting system and passive autocatalytic recombiners allows control of the pressure, radioactive releases, and concentration of flammable gases. Thermal hydraulic analysis of the containment equipped with dedicated passive safety systems after a hypothetical station blackout event is performed for a two-loop pressurized water reactor NPP with three integral severe accident codes: ASTEC, MELCOR, and MAAP. MELCOR and MAAP are two major US codes for severe accident analyses, and the ASTEC code is the European code, joint property of Institut de Radioprotection et de Sûreté Nucléaire (IRSN, France) and Gesellschaft für Anlagen und Reaktorsicherheit (GRS, Germany). Codes’ overall characteristics, physics models, and the analysis results are compared herein. Despite considerable differences between the codes’ modelling features, the general trends of the NPP behaviour are found to be similar, although discrepancies related to simulation of the processes in the containment cavity are also observed and discussed in the paper.
Tesis sobre el tema "Aster code"
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Babišta, Jan. "Tvorba metodiky pro výpočet zbytkových napětí svařence v programovém prostředí Salome Meca". Master's thesis, Vysoké učení technické v Brně. Fakulta strojního inženýrství, 2021. http://www.nusl.cz/ntk/nusl-443769.
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The usage of welding in the process of manufacturing has become very widespread, mainly due to its low cost, versatility and the possibility of its automation. With its expansion comes higher demand for the possibilities of weld evaluation during the phase of design. Nowadays its possible to use tools based on finite element method for such evaluation. But the most commonly used tools are often very expensive. Therefore, the possibility of using Open-Source tool such as Salome-Meca to simulate the welding process as an alternative to commercial software was investigated. The first part of the work deals with the welding process and a description of the formation of residual stresses and deformations. It also deals with the description of the Salome-Meca software environment and the Code-Aster solver. In the next part the capabilities of the software in relation to problem of welding simulation are discussed. Furthermore, the goemetry of solved weldment, welding conditions, material properties and boundary conditions of the calculation are described. And finally, the individual solutions, their results and disadvantages of used approaches.
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Meunier, Sébastien. "Analyse d'erreur a posteriori pour les couplages Hydro-Mécaniques et mise en œuvre dans Code Aster". Phd thesis, Ecole des Ponts ParisTech, 2007. http://pastel.archives-ouvertes.fr/pastel-00003314.
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Staboli, Chiara. "Interpretazione analitica e simulazione numerica di una prova di carico su un palo di fondazione". Master's thesis, Alma Mater Studiorum - Università di Bologna, 2019.
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La presente tesi si inserisce nell’ambito di un programma di ricerca e sviluppo riguardante l’impiego della piattaforma CAE Salome Meca (Code Aster) nel campo della modellazione geotecnica. L’oggetto alla base del lavoro è stato quello di costruire un modello agli elementi finiti con tale programma di calcolo, capace di analizzare la risposta carico-cedimento di un palo, fino a rottura. Tale lavoro è stato svolto con riferimento a un caso studio reale di una fondazione su pali di una civile abitazione costruita nel comune di Bologna.
In questo contesto il primo tema su cui ci è concentrati è stata l’imposizione delle condizioni iniziali. Questo aspetto assume rilevanza soprattutto nel caso di pali trivellati come quelli del caso studio, che in fase di costruzione portano un disturbo nel terreno circostante e una riduzione dello stato tensionale. Il rimaneggiamento nell’intorno del palo impone la scelta di un idoneo elemento di interfaccia palo-terreno, ai fini di una corretta modellazione del problema. In questa tesi si sono in particolare costruiti modelli con elementi thin layer e con due tipi di elementi giunto forniti da Code Aster (JOINT_MECA_RUPT e JOINT_MECA_FROT).
L’ultimo aspetto che influisce sui risultati del modello è il legame costitutivo usato per descrivere il comportamento del terreno. Nello studio proposto, si è scelto di lavorare sia alle tensioni totali con un legame alla Tresca, sia alle tensioni efficaci con un legame alla Mohr Coulomb.
Individuato il modello che meglio descrive il caso studio è quindi stato calcolato il carico di rottura del palo. La parte restante della tesi vede infine un confronto di questo carico ultimo con quello derivato dalle prove di carico a disposizione (metodo di Chin) e dalle formule statiche. Si è infine concluso con un confronto dei risultati sulla base delle norme tecniche vigenti NTC18.
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Anděl, Tomáš. "Analýza vlivu geometrických odchylek polotovaru na následující proces ohýbání". Master's thesis, Vysoké učení technické v Brně. Fakulta strojního inženýrství, 2018. http://www.nusl.cz/ntk/nusl-382553.
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Presented diploma thesis was created in cooperation with Siemens s.r.o., and deals with the analysis of the bending of aluminium sheets which are later used as a conductors of high voltage electrical energy. These parts are completed into assemblies which serves as connectors of particular segments of an electrical network. The problem occurs as a result of incorrect bend, because it is impossible to join these sections properly. The customer would like to verify if the defined tolerances of semi-finished products are sufficient for proper bend and in case they are not, the tolerances should be modified. Due to the requirement for running numerical simulation in one of the open source software, the Salome-Meca program environment was used.
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Le, Nôtre Yvan. "Etude de la réponse dynamique du Bloc Réacteur soumis à une sollicitation extrême : Co-simulation implicite/explicite multi-échelle en temps pour la dynamique du contact". Electronic Thesis or Diss., Lyon, INSA, 2023. http://www.theses.fr/2023ISAL0055.
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Les centrales nucléaires sont une source de production d'énergie importante en France. Cependant, suite aux différents accidents et aux risques encourus avec cette technologie, la sûreté nucléaire est une préoccupation mondiale. En France, des normes sont imposées continuellement sur les installations nucléaires existantes et sur les prochaines générations en développement. Parmi les nombreux aspects de la sûreté nucléaire, le dimensionnement des structures mécaniques est un sujet important pour les acteurs industriels. L'activité principale de l'entreprise Framatome concerne le dimensionnement et la justification des centrales nucléaires. Celles-ci doivent être conçues pour résister à des conditions extrêmes d'utilisation telles que des séismes, des crashs d'avion ou encore des ruptures de tuyauterie. La modélisation numérique de ce type de chargement passe par des analyses dynamiques temporelles afin de considérer ces phénomènes multi-échelles en temps. Cependant, réaliser ces analyses demande beaucoup de temps CPU et de mémoire. L'objectif de la thèse est le développement d'un nouvel intégrateur hétérogène (différents schémas d'intégration) asynchrone (différents pas de temps), basé sur la méthode de couplage GC, ayant de meilleures propriétés relatives à la conservation énergétique. En effet, les phénomènes multi-échelles en temps présents dans le bloc réacteur sont des cas d'usages favorables aux méthodes multi-échelles en temps, avec un intégrateur explicite pour les zones de contact, comportant une discrétisation temporelle fine, et un intégrateur implicite pour le reste de la structure, discrétisé par des pas de temps plus gros. Un démonstrateur de co-simulation est développé entre les logiciels Code Aster et Europlexus pour se rapprocher d'un développement industriel et ainsi montrer le gain de performance, pour un modèle tridimensionnel de bloc réacteur, apporté par les approches de co-simulation multi-échelles en tempsNuclear power plants are an important source of energy production in France. However, following the various accidents and risks associated with this technology, nuclear safety is a global concern. In France, standards are continually being imposed on existing nuclear facilities and on the next generations under development. Among the many aspects of nuclear safety, the dimensioning of mechanical structures is an important subject for industrial players. Framatome's core business is the design and justification of nuclear power plants. These must be designed to withstand extreme operating conditions, such as earthquakes, plane crashes or pipe ruptures. Numerical modeling of this type of loading requires dynamic temporal analyses to consider these multi-scale phenomena. However, such analyses are CPU and memory intensive. The aim of this thesis is to develop a new heterogeneous (different integration schemes) and asynchronous (different time steps) integrator, based on the GC coupling method, with improved energy conservation properties. The multi-scale phenomena present in the reactor block are simulated using an explicit integrator with small time steps for the contact zones and an implicit integrator with large time steps for the rest of the structure. A co-simulation demonstrator is developed between the Code Aster and Europlexus software packages in order to get closer to an industrial development and thus demonstrate the performance gain, for a three-dimensional reactor block model, provided by the multi-time-scale co-simulation approaches
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Tarozzi, Alessandro. "Modellazione 3D e analisi dello stato tenso-deformativo di una calandra per la produzione di tubi di acciaio a saldatura elicoidale". Bachelor's thesis, Alma Mater Studiorum - Università di Bologna, 2016. http://amslaurea.unibo.it/11814/.
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Il lavoro di indagine che è stato sviluppato nella presente tesi è volto a valutare, attraverso metodi FEM, ossia tecniche numeriche computazionali, le sollecitazioni e le deformazioni che agiscono sul telaio di uno "Stampo", macchina che realizza l'operazione di calandratura della lamiera nella produzione di tubi di acciaio a saldatura elicoidale. In particolare l’analisi riportata in questo documento può ritenersi uno studio preliminare che ha lo scopo di creare un simulatore tenso-deformativo che permetta di realizzare un futuro lavoro di validazione del modello, quindi esso è stato realizzato nel modo più flessibile possibile, in modo che sia agevole, anche in un secondo tempo, introdurvi delle modifiche. Il Software utilizzato per la realizzazione dell'analisi FEM è Salomé-Meca accompagnato dal risolutore Code Aster. Oltre all'analisi sul Telaio dello Stampo si è effettuato uno studio preliminare, di validità generale, in cui si riportano in dettaglio le operazioni da effettuare per lo studio degli Assembly. In particolare è stato utilizzato il software Efficient per la creazione del file di comando.
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Saberi, Sina. "Analysis of Unreinforced and Reinforced Tubular T-Joints Structures with Open Source Finite Element Software". Master's thesis, Alma Mater Studiorum - Università di Bologna, 2021.
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Tubular Joints play quite a vital role in most of the marine structures. It is obvious that having full control about the capacity and strength of tubular joints would be very worthy to have good knowledge about the total performance of the structure. In recent years the application of the finite element method has become very popular in the analyses of different types of welded circular tubular joints. The rapid development of FE programs and computation facilities has extended the analyses in the study of stress distribution and load-displacement behavior of a joint to the assessment of the ultimate capacity. This thesis presents a numerical investigation using open source finite element analysis on tubular joints that are the main structural components of steel offshore structures. The studied joint is reinforced and unreinforced T-joint. In nowadays, several types of reinforcement are available to enhance the strength of tubular joints. Thus, for a better understanding of the static strength of joints, two common types of reinforcement plate (doubler and collar) were investigated. In this regards twelve T-Joint specimens subjected to axial brace load (6 in compression and 6 in tension) have been studied, with the different geometric, material property, and reinforced plate. In addition, different types of shell and solid finite elements are considered in this investigation. The shell elements are the linear triangular and quadrilateral elements and the solid elements are the linear tetrahedral and hexahedral elements. Also, this study was performed to investigate and report the usefulness of the open-source software programs Code\_Aster and Salome-Meca in implementing static finite element modeling of tubular joints.
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Tedros, Benhur Bahta. "Application of Advanced Spaceborne Thermal Emission and Reflection Radiometer (ASTER) data to the Mapping of Minerals associated with Hydrothermally Altered Rocks in the Zara Gold Prospects, Eritrea, NE Africa". Bowling Green State University / OhioLINK, 2011. http://rave.ohiolink.edu/etdc/view?acc_num=bgsu1294520796.
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Gómez, García-Toraño Ignacio [Verfasser] y R. [Akademischer Betreuer] Stieglitz. "Further development of Severe Accident Management Strategies for a German PWR Konvoi Plant based on the European Severe Accident Code ASTEC / Ignacio Gómez García-Toraño ; Betreuer: R. Stieglitz". Karlsruhe : KIT-Bibliothek, 2017. http://d-nb.info/1140118420/34.
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"Assinaturas espectrais de gossans associados a mineralizações de Pb-Zn-Ba na Bacia de Irece (BA) : um estudo baseado em dados de sensores TM e ASTER". Tese, Biblioteca Digital da Unicamp, 2003. http://libdigi.unicamp.br/document/?code=vtls000305147.
Texto completoLibros sobre el tema "Aster code"
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Yamano, N. Aerosol Sampling and Transport Efficiency Calculation (ASTEC) and application to surtsey/DCH aerosol sampling system: Code version 1.0 : code description and user's manual. Washington, DC: Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1989.
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Ḳarp, Mosheh Mordekhai. Kinʼat sofrim: Odot tiḳun sofrim : ʻal Nakh ṿe-4 megilot ʻa. p. Keter Aram tsova ha-meyuḥas le-Ben Asher. Yerushalayim: Mekhon Daʻat u-tevunah, 1995.
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Ben-Asher, Aaron ben Moses, 10th cent y Dotan Aron 1928-, eds. [Torah Neviʾim u-Khetuvim] =: Biblia Hebraica Leningradensia : prepared according to the vocalization, accents, and masora of Aaron ben Moses ben Asher in the Leningrad Codex. Peabody: Hendrickson Publishers, 2001.
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Ṭaʻame 21 sefarim: A treatise on the accentuation of the twenty-one so-called prose books of the Old Testament : with a facsimile of a page of the codex assigned to Ben-Asher in Aleppo. Oxford: Clarendon Press, 1989.
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Dolph's Map, Lake County, Florida: Including Astatula, Astor, Clermont, Eustis ... Featuring Golf Courses ... Zip Codes. Not Avail, 2005.
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Asten, Maureen A. Lesbian Family Relationships in American Society. Greenwood Publishing Group, Inc., 1997. http://dx.doi.org/10.5040/9798400678325.
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This book explores intimate relationships in lesbian families living in American society. From an insider's point of view, it examines how relationships within these families form and develop, what special concerns and problems result, what personal gains the family members derive from these types of families, and how motherhood and parenthood evolve. This work is a companion to Dr. Asten's ethnographic video, Intimate Relationships in Three Lesbian Families Living in American Society. Most of the literature on lesbian families compares heterosexual families to lesbian families and uses the researcher's perspective as the core unit of analysis. In contrast, this work is an interrelated filmed/written ethnography which is the result of participant observation and feminist participatory research. It includes not only the researcher's data analysis but also the participants' reaction to and interaction with the process. Providing a unique understanding of the diversity of the American family, this is an important contribution to the growing fields of lesbian/feminist studies and visual anthropology, as well as sociology and psychology. For a copy of the video, Intimate Relationships in Three Lesbian Families Living in American Society, that accompanies this book, contact Dr. Maureen A. Asten, 1 Fifth Avenue, Shrewsbury, MA 01545. Telephone: (508) 799-9746.
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Dotan, Aron. Biblia Hebraica Leningradensia: Prepared According to the Vocalization, Accents, and Masora of Aaron Ben Moses Ben Asher in the Leningrad Codex. Hendrickson Publishers Marketing, LLC, 2018.
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Dotan, Aron. Biblia Hebraica Leningradensia: Prepared according to the Vocalization, Accents, and Masora of Aaron ben Moses ben Asher in the Leningrad Codex. Hendrickson Publishers, 2001.
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Dotan, Aron. Biblia Hebraica Leningradensia: Prepared According to the Vocalization, Accents, and Masora of Aaron Ben Moses Ben Asher on the Leningrad Codex. Brill Academic Publishers, 2000.
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William, Wickes. Treatise on the Accentuation of the Twenty-One So-Called Prose Books of the Old Testament: With a Facsimile of a Page of the Codex Assigned to Ben-Asher in Aleppo. Wipf & Stock Publishers, 2010.
Buscar texto completoCapítulos de libros sobre el tema "Aster code"
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Oschütz, Frank. "Doping Cases Before the Cas and the World Anti-Doping Code". En ASSER International Sports Law Series, 246–65. The Hague: T.M.C. Asser Press, 2006. http://dx.doi.org/10.1007/978-90-6704-591-9_20.
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Weigel, Andreas, Thorben Lukas Baumgart, Michael Heinlein, Norbert Huchler, Björn Niehaves, Louisa Sauter, Anne Schmallenbach, Benjamin Staiger y Regina Wittal. "Arbeitsgestaltung durch Kompetenzvermittlung in VR". En Digitalisierung der Arbeitswelt im Mittelstand 2, 183–214. Berlin, Heidelberg: Springer Berlin Heidelberg, 2022. http://dx.doi.org/10.1007/978-3-662-65858-1_6.
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ZusammenfassungDie Arbeitswelt und ihre Gestaltung befinden sich in einem stetigen Wandel. Der Einsatz neuer Technologien trägt dazu bei, die Innovationskraft und auch die allgemeine Attraktivität eines Unternehmens zu steigern. Dennoch müssen Unternehmen abwägen, ob ein solcher Einsatz auch unter wirtschaftlichen Gesichtspunkten erfolgsversprechend ist. VR-Technologien sind in den letzten Jahren deutlich erschwinglicher geworden und ihre Einsatzgebiete haben sich kontinuierlich weiterentwickelt. Die Gestaltung von virtuellen Umgebungen bietet umfangreiche Möglichkeiten. So nutzen Unternehmen virtuelle Showrooms zur Unterstützung des Verkaufsprozesses, setzen VR-Trainingsszenarien für die Aus- und Weiterbildung ihrer Mitarbeiter*innen ein, planen virtuelle Veranstaltungen als Antwort auf die Restriktionen der COVID-19 Pandemie oder beschäftigen sich mit virtuellen Kompetenzassistenten. Die Potentiale von VR-Technologien sind dabei weitreichend und können durch einen gezielten Einsatz vielversprechende Lösungen bieten. Das Projekt aSTAR verfolgte das Ziel, die Kompetenzvermittlung zwischen Konstrukteur*innen und Servicemitarbeiter*innen durch eine VR-Technologie zu unterstützen. Zu diesem Zweck wurden zunächst VR-Simulationen der Montage- und Wartungsszenarien am Kran entwickelt. Im Verlauf des Projektes entstand parallel eine VR-Software, die eine individuelle Gestaltung der VR-Umgebung ermöglicht. In die Software können unterschiedliche Kranmodelle sowie Umgebungen und Objekte geladen und flexibel platziert werden. Anschließend lassen sich Arbeitsschritte und -abläufe definieren, welche dann in der VR-Umgebung erlebt und bearbeitet werden können. Darüber hinaus sollte durch die VR-Entwicklung eine Möglichkeit entstehen, den CAD-Entwurf einfach in die VR zu übertragen (CAD2VR). Dies würde es den Konstrukteur*innen erlauben, ihren CAD-Entwurf in die VR zu laden und diesen dort aus einer Montage- und Serviceperspektive zu bewerten und bei Bedarf anzupassen. Durch die kontinuierliche Evaluation und Erhebung qualitativer Daten durch die Endanwender*innen konnte die Integration der VR-Technologie in bestehende Arbeitsprozesse aus vielen Perspektiven betrachtet werden. Somit können nun Strategien und Richtlinien formuliert werden, die die Integration der genannten VR-Szenarien und der CAD2VR-Anwendung unterstützen und übertragbare Ansätze für die Praxis liefern. Zusätzlich zu den VR-Technologien wurde eine Wissensplattform für die Montage- und Wartung am Kran aufgesetzt. Diese hatte zum Ziel, basierend auf einem intelligenten Suchalgorithmus, durch das Scannen von z. B. QR-Codes Informationen (Bedienungsanleitungen, Zusatzinformationen für bestimmte Krantypen) zur Montage- und Wartungsunterstützung bereitzustellen.
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"ASTER Brightness and Ratio Codes for Minerals". En Remote Sensing and Spectral Geology, 143–68. Society of Economic Geologists, 2009. http://dx.doi.org/10.5382/rev.16.12.
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Wohl, Ellen. "September: Alternate Realities". En Saving the Dammed. Oxford University Press, 2019. http://dx.doi.org/10.1093/oso/9780190943523.003.0012.
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The first week of September mostly feels like summer. The air on the dry terrace bordering the beaver meadow is richly scented with pine. Purple aster, blue harebells, and tall, yellow black-eyed Susan still bloom. Fungi are more abundant on the forest floor, and the tiny, purplish berries of kinnikinnick are sweet to the taste. The air is warm in the sunshine, but strong winds hurry rain showers through at intervals. Patches of last year’s snow linger on the surrounding peaks, even as the first light snows have already fallen in the high country. Down in the beaver meadow, the leaves of aspen, willow, birch, and alder are starting to assume their autumn colors. Here and there a small patch of yellow or orange appears among the green. Blades of grass have a pale orange tint and the strawberry leaves have gone scarlet, even as white asters, purple thistles, and a few other flowers continue to bloom. The creek is noticeably lower, its cobble bed slick with rust-brown algae. Exposed cobble and sandbars have grown wider as the water has shrunk back from the edge of the willows, and the main channel is easy to cross on foot. The clear water is chillingly cold in both the main channel and the side channels. The smaller side channels no longer flow, and a drape of mud mixed with bits of plants covers the cobbles. Wood deposited a year ago has weathered to pale gray. The older, marginal beaver ponds have shrunk noticeably, and the water is lower in the main ponds, where tall sedges now lie bent on the top of the declining water surface. The beavers remain active: following fresh moose tracks, I come on a newly built beaver dam on a small side channel. By the third week of September, autumn has clearly arrived in the mountains. The air remains quite warm during the day, but nights of frost are swiftly bringing out the autumn colors. Whole stands of willows and aspen now glow golden or pumpkin-orange.
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Novak, Barbara. "Asher B. Durand: Hudson River School Solutions". En American Painting of the Nineteenth Century, 59–70. Oxford University PressNew York, NY, 2007. http://dx.doi.org/10.1093/oso/9780195309423.003.0004.
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Abstract In the hands of Thomas Cole’s successors, the development of an official Hudson River style seems to have been the natural result of the general public pressure for fulfillment of the hybrid aesthetic of the real-ideal. Some critics, such as Jarves, would have preferred the idealism of Cole: . . . in all his work we find the artist actuated rather by a lofty conception of the value of art as a teacher than by an ambition to excel in mere imitation. With him American landscape art began its career with high motives. Progress in this direction requires no ordinary degree of thought and imagination. It is, perhaps, on this account that he is not popularly estimated at his right value, and has left no followers to carry forward the beautiful significance and lofty suggestion with which he aimed to endow landscape art.
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Tierce, P. y P. Robache. "PIEZOELECTRIC TRANSDUCER ANALYSIS USING THE TRANSFER MATRIX METHOD AND A VERSATILE COMPUTER CODE: ASTRE". En Ultrasonics International 91, 431–34. Elsevier, 1991. http://dx.doi.org/10.1016/b978-0-7506-0389-8.50101-3.
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Bass, Christopher y David Gill. "Factitious disorder and malingering". En New Oxford Textbook of Psychiatry, 1049–59. Oxford University Press, 2012. http://dx.doi.org/10.1093/med/9780199696758.003.0135.
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Patients with factitious disorder feign or simulate illness, are considered not to be aware of the motives that drive them to carry out this behaviour, and keep their simulation or induction of illness secret. In official psychiatric nomenclature, factitious disorder has replaced the eponym Munchausen syndrome, introduced by Asher to describe patients with chronic factitious behaviour. Asher borrowed the term from Raspe's 1785 fictional German cavalry officer, Baron Karl von Munchausen, who always lied, albeit harmlessly, about his extraordinary military exploits. The criteria for factitious disorder in DSM-IV are (a) the intentional production or feigning of physical or psychological signs or symptoms; (b) motivation to assume the sick role; and (c) lack of external incentives for the behaviour (e.g. economic gain, avoidance of legal responsibility, or improved physical well-being, as in malingering) and lack of a better classification for the disorders. In the last 10 years there has been increased interest in deception in medical practice, with specific focus on pathological lying and the diagnostic dilemmas in this field: specifically, how to differentiate between hysteria, factitious disorders, and malingering. Some of these topics will be discussed in the next section. This chapter concentrates on factitious physical complaints; fabricated psychological symptoms are considered under malingering. The DSM-IV criteria have recently come under attack. Turner has argued that criterion B (motivation to assume the sick role) has no empirical content and fulfils no diagnostic function. He also argues that criterion A, the intentional production of physical or psychological signs or symptoms, emphasizes symptoms and cannot accommodate pseudologia fantastica (PF), voluntary false confessions, and impersonations. He concludes that the two criteria need reformulating in terms of lies and self-harm, respectively. Bass and Halligan have also suggested that because the conceptual justification for factitious disorders is ‘empirically unsubstantiated’ and the motivation for diagnostic purposes (conscious versus unconscious; voluntary versus involuntary) essentially unknowable, it seems reasonable to question the clinical status and legitimacy of factitious disorder. More recently there has been a resurgence of interest in pathological lying, because this is often easier to identify than, for example, the degree of ‘voluntariness’ or ‘motivation’ to attain the sick role (however that is defined).
Actas de conferencias sobre el tema "Aster code"
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Métais, Thomas, Sarah Plessis, The-Hiep Chau y Jean-Christophe Le Roux. "Evolution of Fatigue Post-Processing Methods in the EDF Open-Access FEA Code ASTER". En ASME 2016 Pressure Vessels and Piping Conference. American Society of Mechanical Engineers, 2016. http://dx.doi.org/10.1115/pvp2016-63126.
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Fatigue is identified as a significant degradation mode that affects nuclear power plants world-wide. The various international codes and standards (ASME, RCC-M, JSME, etc...) offer rules to predict its damaging effect on the locations of the various components of an NPP. These rules, which ensure conservatism and safe operation, have grown in complexity over the years because they have integrated R&D results showing aggravating effects that were not included in the original analyses (such as Environmental Assisted Fatigue [1]) but also because an economically viable design of components has required optimization and refinement of mechanical assessment methods. EDF has been developing since 1989 its own open-source FEA code baptised code ASTER that is included in the Salome Meca mechanical package. Salome Meca is open-access and can be used freely by international users. It is continuously improved with a release at a rate of one new software version per year and it integrates the most recent results obtained by the EDF R&D, in fields as broad as fracture mechanics, XFEM and fatigue. The fatigue post-processing in code ASTER offers a span of criteria (Dang Van, Stress Intensity, etc...) to pick and choose from and even offers the possibility to make up one owns fatigue criteria. It also offers the possibility to post-process fatigue according to the RCC-M rules (POST_RCCM operator). Recent developments have enabled to update the POST_RCCM operator to make it bridge the gap with modern fatigue industrial codes as well as to integrate the EAF calculations per the methodology proposed in [2]. The work is currently ongoing within EDF R&D and will give birth to a stabilized and validated version of the code by end of 2016. This paper presents the updates and the new possibilities of the POST_RCCM operator and gives an update of the work as of early 2016.
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Ivanov, Dmitry, John Inge Asperheim y Leif Markegård. "Residual Stress Distribution in Induction Hardened Gear". En HT 2015. ASM International, 2015. http://dx.doi.org/10.31399/asm.cp.ht2015p0029.
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Abstract The development of residual stress in an induction hardened small spur gear is numerically simulated. A full scale 3D simulation is utilized to obtain the results, providing the possibility to evaluate the complete distribution of residual stress in the hardened component. Electromagnetic and thermal solutions under induction heating conditions are obtained with Cedrat Flux 3D, whereas EDF Code Aster software is used for thermal simulation during the quenching stage, phase transformation, and stress-strain simulations. The simulated induction heating isotherms and distribution of residual stress are compared with experimental investigations done by Larregain et al. and Savaria et al.
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Van Dorsselaere, J. P. "Applications of ASTEC Integral Code in the SARNET Network". En 16th International Conference on Nuclear Engineering. ASMEDC, 2008. http://dx.doi.org/10.1115/icone16-48354.
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The ASTEC integral code is being developed by IRSN (France) and GRS (Germany) for simulation of severe accidents (SA) in Light Water reactors (LWR): safety studies including the evaluation of source term, Probabilistic Safety Analysis level 2 (PSA2) and assessment of SA management actions. It plays a key-role in the SARNET Network of Excellence on R&D on severe accidents (2004–2008) of the 6th Framework Programme of the European Commission. A substantial effort is being made to disseminate ASTEC and to perform jointly-executed research activities with the ultimate objective of providing physical models for integration into ASTEC and making it the European reference integral code. Thirty partners are assessing the ASTEC V1 successive versions through validation against experiments and benchmarks on plant applications with integral and mechanistic codes. This paper presents an overview of the work done in 2006 with the version ASTEC V1.2rev1 released by IRSN and GRS in Dec.05. In particular, this version included improvements of the documentation, mainly users manuals and guidelines, and CEA model improvements for the corium behaviour in the vessel lower head. For ASTEC adaptation to BWR and CANDU, the needs concern mainly the in-vessel core degradation and the corresponding specifications are being written. As to ASTEC validation, applications were performed on the following physical phenomena and experiments: circuit thermalhydraulics (PACTEL T2.1 and ISP33, PMK2, LOFT-LP-FP2); core degradation (CORA-13 and W2, QUENCH-11, LOFT-LP-FP2, Phe´bus FPT4); fission products release and transport (COLIMA, STORM, Phe´bus FPT0-1-2); Molten-Corium-Concrete-Interaction or MCCI (ACE L4, BETA, OECD-CCI2); containment thermalhydraulics and aerosol behaviour (LACE LA4, ThAI, PACOS Px1.2); and iodine in a multi-compartment containment (ThAI). The results are in general good, often close to results of mechanistic codes. Some models reach the limits of present international knowledge, for instance MCCI and hydrogen production during the reflooding of a degraded core. As to ASTEC benchmarking, applications for diverse accident scenarios (LOCA, Loss of Steam Generator Feedwater and SBO) were performed for several reactor types: PWR 900, Konvoi 1300, Westinghouse 1000, VVER-1000 and VVER-440. The main trends of results are similar to results obtained with MELCOR or MAAP4 codes. Some quantitative differences are due to modelling differences, i.e. on core degradation. The preliminary comparison on fission products results will be extended in 2007–08. Good results were obtained in the comparison with mechanistic codes such as ATHLET-CD, RELAP5-3D or COCOSYS. Exploratory calculations on VVER-440 showed the ASTEC capabilities to evaluate the possibilities of In-Vessel Melt Retention. For CANDU reactors, physically reliable results were obtained on fission products transport and behaviour. The ASTEC V1 code evolution will now be limited to feedback from the IRSN current Probabilistic Safety Analysis level 2 on 1300 MWe reactors and from SARNET applications. From now on, IRSN and GRS are preparing the new series V2 of ASTEC versions, taking into account the code evolution needs as expressed by the SARNET users. The first V2.0 release is planned at the end of 2008: the version will be applicable to EPR and will include the advanced core degradation models of the ICARE2 mechanistic IRSN code. In 2008, the partners will switch to the assessment of the V1.3rev2 version that was delivered in Dec.2007 and present their results at the 3rd ASTEC Users’ Club organised by IRSN in April 2008.
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De Rosa, Felice. "Application of MELCOR Code to a French PWR 900 MWe Severe Accident Sequence and Evaluation of Models Performance Focusing on In-Vessel Thermal Hydraulic Results". En 14th International Conference on Nuclear Engineering. ASMEDC, 2006. http://dx.doi.org/10.1115/icone14-89731.
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In the ambit of the Severe Accident Network of Excellence Project (SARNET), funded by the European Union, 6th FISA (Fission Safety) Programme, one of the main tasks is the development and validation of the European Accident Source Term Evaluation Code (ASTEC Code). One of the reference codes used to compare ASTEC results, coming from experimental and Reactor Plant applications, is MELCOR. ENEA is a SARNET member and also an ASTEC and MELCOR user. During the first 18 months of this project, we performed a series of MELCOR and ASTEC calculations referring to a French PWR 900 MWe and to the accident sequence of “Loss of Steam Generator (SG) Feedwater” (known as H2 sequence in the French classification). H2 is an accident sequence substantially equivalent to a Station Blackout scenario, like a TMLB accident, with the only difference that in H2 sequence the scram is forced to occur with a delay of 28 seconds. The main events during the accident sequence are a loss of normal and auxiliary SG feedwater (0 s), followed by a scram when the water level in SG is equal or less than 0.7 m (after 28 seconds). There is also a main coolant pumps trip when ΔTsat < 10 °C, a total opening of the three relief valves when Tric (core maximal outlet temperature) is above 603 K (330 °C) and accumulators isolation when primary pressure goes below 1.5 MPa (15 bar). Among many other points, it is worth noting that this was the first time that a MELCOR 1.8.5 input deck was available for a French PWR 900. The main ENEA effort in this period was devoted to prepare the MELCOR input deck using the code version v.1.8.5 (build QZ Oct 2000 with the latest patch 185003 Oct 2001). The input deck, completely new, was prepared taking into account structure, data and same conditions as those found inside ASTEC input decks. The main goal of the work presented in this paper is to put in evidence where and when MELCOR provides good enough results and why, in some cases mainly referring to its specific models (candling, corium pool behaviour, etc.) they were less good. A future work will be the preparation of an input deck for the new MELCOR 1.8.6. and to perform a code-to-code comparison with ASTEC v1.2 rev. 1.
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Lindstro¨m, Per R. M. y Maneli Faraji. "Review and Selection of a Finite Element Simulation Platform for Academic and Industrial Analyses of In-Service Welding Operations". En ASME 2004 23rd International Conference on Offshore Mechanics and Arctic Engineering. ASMEDC, 2004. http://dx.doi.org/10.1115/omae2004-51246.
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In order find a general platform/environment for simulation of in-service welding operations, a review and analysis of non-linear Finite Element Analysis, FEA, programs have been performed. Free and commercial softwares have been considered and the programs that have been reviewed and evaluated are ABAQUS, CALCULIX, CODE-ASTER, MARC and SYSWELD. Different platforms, i.e. workstation configurations with the associated Operative System, OS, has also been investigated to find an optimised simulation platform solution. To facilitate the selection of a suitable simulation platform, the performance and durability of ABAQUS has been evaluated by means of an in-service weld simulation. The residual weld hoop stresses of the weld simulation have been compared with the results of girth weld experiments from bibliographic sources. To enhance the evaluation process as well as gain experiences of measuring residual weld stresses, two (2) girth welds with measurement of the weld hoop stresses have been carried out. The maximum solving performance of ABAQUS was obtained by means of a tailor-made workstation, configured with the OS Slackware Linux 9.1 and a specially compiled Linux kernel. The findings of the research will be utilized on selection of a FEA-simulation platform that will be used for the purpose of scientific research and industrial development in the field of inservice welding operations.
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Tusheva, Polina, Nils Reinke, Eberhard Altstadt, Frank Schaefer, Frank-Peter Weiss y Antonio Hurtado. "Analysis of Severe Accidents in VVER-1000 Reactors Using the Integral Code ASTEC". En 17th International Conference on Nuclear Engineering. ASMEDC, 2009. http://dx.doi.org/10.1115/icone17-75563.
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The studies presented are aiming at a detailed investigation of the behaviour of a VVER-1000/V-320 reactor and the containment structures during a postulated severe accident, including the ways and means by which these accidents may be prevented or mitigated. A hypothetical station blackout scenario (loss of the offsite electric power system concurrent with a turbine trip and unavailability of the emergency AC power system), belonging to the typical beyond design basis accidents, has been investigated. Station blackout results in reactor shut down, loss of feed water and trip of all reactor coolant pumps. Continuous evaporation of the secondary side leads to steam generators’ depletion followed by heating up of the core. In case of unavailability of essential safety systems the core will be severely damaged and finally the reactor pressure vessel (RPV) might fail. The analyses are performed using the integral code ASTEC commonly developed by IRSN (Institut de Radioprotection et de Suˆrete´ Nucle´aire) and GRS (Gesellschaft fu¨r Anlagen- und Reaktorsicherheit mbH). Code-to-code comparative analyses for the early thermal-hydraulic phase have been performed with the GRS code ATHLET. A large number of sensitivity calculations have been done regarding the axial core power distribution, heat losses, and RPV lower head modelling. The analyses have shown that, despite the considerable differences in the codes themselves, the calculation results are similar in terms of thermal hydraulic response. There are discrepancies in timings of phenomena, which are within the limitations of the physical models and the applied nodalizations. It was one objective of this investigation to evaluate the Severe Accident Management (SAM) procedures for VVER-1000 reactors, by for instance estimating the time available for taking appropriate decisions and preparing counter-measures. To evaluate the effect of possible operator actions, a SAM procedure (primary side depressurization) is included into the simulation. Without SAMs, the simulation provides plastic rupture of the RPV after approximately 4.3 h, while with SAMs, a prolongation of the vessel failure time is obtained by approximately 90 minutes. Currently, the late phase of the accident is investigated in more detail by comparing the lower head behaviour as simulated by ASTEC with results from dedicated finite element calculations. The work contributes to the reliability of the ASTEC code by means of plant applications.
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Caroli, Cataldo, Alexandre Bleyer, Ahmed Bentaib, Patrick Chatelard, Michel Cranga y Jean-Pierre Van Dorsselaere. "The Development of Severe Accident Codes at IRSN and Their Application to Support the Safety Assessment of EPR". En 14th International Conference on Nuclear Engineering. ASMEDC, 2006. http://dx.doi.org/10.1115/icone14-89461.
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IRSN uses a two-tier approach for development of codes analysing the course of a hypothetical severe accident (SA) in a Pressurized Water Reactor (PWR): on one hand, the integral code ASTEC, jointly developed by IRSN and GRS, for fast-running and complete analysis of a sequence; on the other hand, detailed codes for best-estimate analysis of some phenomena such as ICARE/CATHARE, MC3D (for steam explosion), CROCO and TONUS. They have been extensively used to support the level 2 Probabilistic Safety Assessment of the 900 MWe PWR and, in general, for the safety analysis of the French PWR. In particular the codes ICARE/CATHARE, CROCO, MEDICIS (module of ASTEC) and TONUS are used to support the safety assessment of the European Pressurized Reactor (EPR). The ICARE/CATHARE code system has been developed for the detailed evaluation of SA consequences in a PWR primary system. It is composed of the coupling of the core degradation IRSN code ICARE2 and of the thermalhydraulics French code CATHARE2. The CFD code CROCO describes the corium flow in the spreading compartment. Heat transfer to the surrounding atmosphere and to the basemat, leading to the possible formation of an upper and lower crust, basemat ablation and gas sparging through the flow are modelled. CROCO has been validated against a wide experimental basis, including the CORINE, KATS and VULCANO programs. MEDICIS simulates MCCI (Molten-Corium-Concrete-Interaction) using a lumped-parameter approach. Its models are being continuously improved through the interpretation of most MCCI experiments (OECD-CCI, ACE…). The TONUS code has been developed by IRSN in collaboration with CEA for the analysis of the hydrogen risk (both distribution and combustion) in the reactor containment. The analyses carried out to support the EPR safety assessment are based on a CFD formulation. At this purpose a low-Mach number multi-component Navier-Stokes solver is used to analyse the hydrogen distribution. Presence of air, steam and hydrogen is considered as well as turbulence, condensation and heat transfer in the containment walls. Passive autocatalytic recombiners are also modelled. Hydrogen combustion is afterwards analysed solving the compressible Euler equations coupled with combustion models. Examples of on-going applications of these codes to the EPR safety analysis are presented to illustrate their potentialities.
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Kaliatka, Tadas, Eugenijus Ušpuras y Virginijus Vileiniškis. "Best Estimate Analysis of PHEBUS FPT1 Test Using RELAP/SCDAPSIM Code". En 2012 20th International Conference on Nuclear Engineering and the ASME 2012 Power Conference. American Society of Mechanical Engineers, 2012. http://dx.doi.org/10.1115/icone20-power2012-54693.
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The PHEBUS-FP program is an outstanding example of an international cooperative research program that is yielding valuable data for validating severe accident analysis computer codes. The main objective of the PHEBUS FPT1 experiment was to study the processes in the overheated reactor core, release of fission products and their subsequent transport and deposition under conditions representative of a severe accident of a Pressurised Water Reactor. The FPT1 test could be divided in the bundle degradation, aerosol, washing and chemistry phases. The objective of this article is the best estimate analysis of the bundle degradation phase. GRS (Germany) best estimate method with the statistic tool SUSA used for uncertainty and sensitivity analysis of calculation results and RELAP/SCDAPSIM code, designed to predict the behaviour of reactor systems during severe accident conditions, was used for the simulation of this test. The RELAP/SCDAPSIM calculation results were compared with the experimental measurements and calculations results, received by employing ICARE module of ASTEC V2 code. The performed analysis demonstrated, that the best estimate method, employing RELAP/SCDAPSIM and SUSA codes, is capable to model main severe accidents phenomena in the fuel bundle during the overheating and melting of reactor core.
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Reinke, N., K. Neu y H. J. Allelein. "ASTEC: An Integral Code for Simulation of Severe Light Water Reactor Accidents". En 14th International Conference on Nuclear Engineering. ASMEDC, 2006. http://dx.doi.org/10.1115/icone14-89280.
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The integral code ASTEC (Accident Source Term Evaluation Code) commonly developed by IRSN and GRS is a fast running programme, which allows the calculation of entire sequences of severe accidents (SA) in light water reactors from the initiating event up to the release of fission products into the environment, thereby covering all important in-vessel and containment phenomena. Thus, the main fields of ASTEC application are intended to be accident sequence studies, uncertainty and sensitivity studies, probabilistic safety analysis level 2 studies as well as support to experiments. The modular structure of ASTEC allows running each module independently and separately, e.g. for separate effects analyses, as well as a combination of multiple modules for coupled effects testing and integral analyses. Among activities concentrating on the validation of individual ASTEC modules describing specific phenomena, the applicability to reactor cases marks an important step in the development of the code. Feasibility studies on plant applications have been performed for several reactor types such as the German Konvoi PWR 1300, the French PWR 900, and the Russian VVER-1000 and −440 with sequences like station blackout, small- or medium-break loss-of-coolant accident, and loss-of-feedwater transients. Subject of this paper is a short overview on the ASTEC code system and its current status with view to the application to severe accidents sequences at several PWRs, exemplified by selected calculations.
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Peschel, Jan M., Christoph Bratfisch y Marco K. Koch. "Analysis of the Reflooding Process in Degraded Particle Beds by Simulations of the Debris Test Facility With the Severe Accident Analysis Code ASTEC V2.1 and COCOMO Code". En 2021 28th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2021. http://dx.doi.org/10.1115/icone28-60964.
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Abstract As part of a national research project RUB PSS investigates the cooling process of degraded core sections like debris beds and melt pools. Focus of these works is the simulation of the DEBRIS test facility located at IKE in Stuttgart with both the integral code ASTEC V2.1, developed by IRSN in France, and COCOMO, developed by IKE. In this work, the simulation of two bottom flooding experiments with similar temperature and pressure conditions but different particle types will be presented. The selected tests will be simulated with both a fixed input signal and a gravity-driven quench water flow similar to the actual test conditions. Focus of the analysis is on a comparison of the calculated and experimental results to validate the codes capabilities to simulate the most relevant phenomena which occur while quenching dry and overheated particle formations under varying thermohydraulic conditions. ASTEC is validated using numerous experiments like the PEARL tests that are comparable to those conducted within the DEBRIS test facility and disposes a well-developed model basis for the simulation of late phase phenomena. The resulting temperature evolutions are in good accordance with the experimental results. This is also reflected by the evolution of the quench front and also applies to the conducted COCOMO simulations. The released amount of steam is overestimated by both codes and leaves room for improvement.
Informes sobre el tema "Aster code"
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Yamano, N. y J. E. Brockmann. Aerosol sampling and Transport Efficiency Calculation (ASTEC) and application to surtsey/DCH aerosol sampling system: Code version 1. 0: Code description and user's manual. Office of Scientific and Technical Information (OSTI), mayo de 1989. http://dx.doi.org/10.2172/6065981.
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Petrova, Petya H. y Pavlin P. Groudev. Analysis of the Fission Products Behaviour in the Phebus FPT1 Experiment by Using the ASTEC V2.1 Code. "Prof. Marin Drinov" Publishing House of Bulgarian Academy of Sciences, mayo de 2019. http://dx.doi.org/10.7546/crabs.2019.05.05.
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