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Artículos de revistas sobre el tema "Aster code"

Autor: Grafiati

Publicado: 25 de mayo de 2024

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1

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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2

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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3

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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4

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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5

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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6

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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7

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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8

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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9

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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10

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.

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11

de la Rosa Blul, J. C., S. Brumm, F. Mascari, S. J. Lee y L. Carenini. "ASTEC–MAAP Comparison of a 2 Inch Cold Leg LOCA until RPV Failure". Science and Technology of Nuclear Installations 2018 (2 de diciembre de 2018): 1–24. http://dx.doi.org/10.1155/2018/9189010.

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A 2 inch, cold-leg loss-of-coolant accident (LOCA) in a 900 MWe generic Western PWR was simulated using ASTEC 2.1.1 and MAAP 5.02. The progression of the accident predicted by the two codes up to the time of vessel failure is compared. It includes the primary system depressurization, accumulator discharge, core heat-up, hydrogen generation, core relocation to lower plenum, and lower head breach. The purpose of the code comparison exercise is to identify modelling differences between the two codes and the user choices affecting the results. The two codes predict similar primary system depressurization behaviour until the accumulation injection, confirming similar break flow and primary system thermal-hydraulic response calculations between the two codes. The choice of the accumulator gas expansion model, either isentropic or isothermal, affects the rate and total amount of coolant injected and thereby determines whether the core is quenched or overheated and attains a noncoolable geometry during reflooding. A sensitivity case was additionally simulated by each code to allow comparisons to be made with either accumulator gas expansion models. The two codes predict similar amount of in-vessel hydrogen generated and core quench status for a given accumulator gas expansion model. ASTEC predicts much larger initial core relocation to lower plenum leading to an earlier vessel failure time. MAAP predicts more gradual core relocation to lower plenum, prolonging the lower plenum debris bed heat-up and time to vessel failure. Beside the effect of the code user in conducting severe accident simulations, some discrepancies are found in the modelling approaches in each code. The biggest differences are found in the in-vessel melt progression and relocation into the lower plenum, which deserve further research to reduce the uncertainties.

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12

Agnello, G., S. Ederli, P. Maccari y F. Mascari. "Analysis of an unmitigated 2-inch cold leg LOCA transient with ASTEC and MELCOR codes". Journal of Physics: Conference Series 2177, n.º 1 (1 de abril de 2022): 012024. http://dx.doi.org/10.1088/1742-6596/2177/1/012024.

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Abstract The analyses of postulated severe accident sequences play a key role for the international nuclear technical scientific community for the study of the effect of possible actions to prevent significant core degradation and mitigate source term release. To simulate the complexity of phenomena involved in a severe accident, computational tools, known as severe accident codes, have been developed in the last decades. In the framework of NUGENIA TA-2 ASCOM project, the analysis of an unmitigated 2-inch cold leg LOCA transient, occurring in a generic western three-loops PWR-900 MWe, has been carried out with the aim to give some insights on the modelling capabilities of these tools and to characterize the differences in the calculations results. The ASTEC V2.2b code (study carried out with ASTEC V2, IRSN all rights reserved, [2021]), and MELCOR 2.2 code have been used in this code-to-code benchmark exercise. In the postulated transient, the unavailability of all active injection coolant systems has been considered and only the injection of accumulators has been assumed as accident mitigation strategy.

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13

Christensen-Dalsgaard, Jørgen. "ASTEC—the Aarhus STellar Evolution Code". Astrophysics and Space Science 316, n.º 1-4 (25 de diciembre de 2007): 13–24. http://dx.doi.org/10.1007/s10509-007-9675-5.

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14

Seehaus, Thorsten, Veniamin I. Morgenshtern, Fabian Hübner, Eberhard Bänsch y Matthias H. Braun. "Novel Techniques for Void Filling in Glacier Elevation Change Data Sets". Remote Sensing 12, n.º 23 (29 de noviembre de 2020): 3917. http://dx.doi.org/10.3390/rs12233917.

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The increasing availability of digital elevation models (DEMs) facilitates the monitoring of glacier mass balances on local and regional scales. Geodetic glacier mass balances are obtained by differentiating DEMs. However, these computations are usually affected by voids in the derived elevation change data sets. Different approaches, using spatial statistics or interpolation techniques, were developed to account for these voids in glacier mass balance estimations. In this study, we apply novel void filling techniques, which are typically used for the reconstruction and retouche of images and photos, for the first time on elevation change maps. We selected 6210 km2 of glacier area in southeast Alaska, USA, covered by two void-free DEMs as the study site to test different inpainting methods. Different artificially voided setups were generated using manually defined voids and a correlation mask based on stereoscopic processing of Advanced Spaceborne Thermal Emission and Reflection Radiometer (ASTER) acquisition. Three “novel” (Telea, Navier–Stokes and shearlet) as well as three “classical” (bilinear interpolation, local and global hypsometric methods) void filling approaches for glacier elevation data sets were implemented and evaluated. The hypsometric approaches showed, in general, the worst performance, leading to high average and local offsets. Telea and Navier–Stokes void filling showed an overall stable and reasonable quality. The best results are obtained for shearlet and bilinear void filling, if certain criteria are met. Considering also computational costs and feasibility, we recommend using the bilinear void filling method in glacier volume change analyses. Moreover, we propose and validate a formula to estimate the uncertainties caused by void filling in glacier volume change computations. The formula is transferable to other study sites, where no ground truth data on the void areas exist, and leads to higher accuracy of the error estimates on void-filled areas. In the spirit of reproducible research, we publish a software repository with the implementation of the novel void filling algorithms and the code reproducing the statistical analysis of the data, along with the data sets themselves.

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15

Povilaitis, Mantas, Egidijus Urbonavicius y Sigitas Rimkevicius. "ICONE19-43654 SIMULATION OF HYDROGEN DEFLAGRATION EXPERIMENTS IN THE ENACCEF FACILITY USING ASTEC CODE". Proceedings of the International Conference on Nuclear Engineering (ICONE) 2011.19 (2011): _ICONE1943. http://dx.doi.org/10.1299/jsmeicone.2011.19._icone1943_263.

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16

Šadek, Siniša y Davor Grgić. "NPP Krško containment modelling with the ASTEC code". Journal of Energy - Energija 64, n.º 1-4 (29 de junio de 2022): 163–77. http://dx.doi.org/10.37798/2015641-4150.

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ASTEC is an integral computer code jointly developed by Institut de Radioprotection et de Sûreté Nucléaire (IRSN, France) and Gesellschaft für Anlagenund Reaktorsicherheit (GRS, Germany) to assess nuclear power plant behaviour during a severe accident (SA). The ASTEC code was used to model and to simulate NPP behaviour during a postulated station blackout accident in the NPP Krško. The accident analysis was focused on containment behaviour; however the complete integral NPP analysis was carried out in order to provide correct boundary conditions for the containment calculation. During the accident, the containment integrity was challenged by release of reactor system coolant through degraded coolant pump seals, molten corium concrete interaction and direct containment heating mechanisms. Impact of those processes on relevant containment parameters, such as compartments pressures and temperatures, is going to be discussed in the paper.

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17

van Dorsselaere, J. P., C. Seropian, P. Chatelard, F. Jacq, J. Fleurot, P. Giordano, N. Reinke, B. Schwinges, H. J. Allelein y W. Luther. "The ASTEC Integral Code for Severe Accident Simulation". Nuclear Technology 165, n.º 3 (marzo de 2009): 293–307. http://dx.doi.org/10.13182/nt09-a4102.

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18

Allelein, H. J., K. Neu y J. P. Van Dorsselaere. "European Validation of the Integral Code ASTEC (EVITA)". Nuclear Engineering and Design 235, n.º 2-4 (febrero de 2005): 285–308. http://dx.doi.org/10.1016/j.nucengdes.2004.08.051.

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19

Allelein, H. J., K. Neu, J. P. Van Dorsselaere, K. Müller, P. Kostka, M. Barnak, P. Matejovic, A. Bujan y J. Slaby. "European validation of the integral code ASTEC (EVITA)". Nuclear Engineering and Design 221, n.º 1-3 (abril de 2003): 95–118. http://dx.doi.org/10.1016/s0029-5493(02)00346-1.

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20

Tregoures, Nicolas, Giacomino Bandini, Laurent Foucher, Joelle Fleurot y Paride Meloni. "ICONE15-10417 VALIDATION OF CESAR THERMAL-HYDRAULIC MODULE OF ASTEC V1.2 CODE ON BETHSY EXPERIMENTS". Proceedings of the International Conference on Nuclear Engineering (ICONE) 2007.15 (2007): _ICONE1510. http://dx.doi.org/10.1299/jsmeicone.2007.15._icone1510_218.

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21

Kitambo, Benjamin M., Fabrice Papa, Adrien Paris, Raphael M. Tshimanga, Frederic Frappart, Stephane Calmant, Omid Elmi et al. "A long-term monthly surface water storage dataset for the Congo basin from 1992 to 2015". Earth System Science Data 15, n.º 7 (12 de julio de 2023): 2957–82. http://dx.doi.org/10.5194/essd-15-2957-2023.

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Abstract. The spatio-temporal variation of surface water storage (SWS) in the Congo River basin (CRB), the second-largest watershed in the world, remains widely unknown. In this study, satellite-derived observations are combined to estimate SWS dynamics at the CRB and sub-basin scales over 1992–2015. Two methods are employed. The first one combines surface water extent (SWE) from the Global Inundation Extent from Multi-Satellite (GIEMS-2) dataset and the long-term satellite-derived surface water height from multi-mission radar altimetry. The second one, based on the hypsometric curve approach, combines SWE from GIEMS-2 with topographic data from four global digital elevation models (DEMs), namely the Terra Advanced Spaceborne Thermal Emission and Reflection Radiometer (ASTER), Advanced Land Observing Satellite (ALOS), Multi-Error-Removed Improved Terrain (MERIT), and Forest And Buildings removed Copernicus DEM (FABDEM). The results provide SWS variations at monthly time steps from 1992 to 2015 characterized by a strong seasonal and interannual variability with an annual mean amplitude of ∼101±23 km3. The Middle Congo sub-basin shows a higher mean annual amplitude (∼71±15 km3). The comparison of SWS derived from the two methods and four DEMs shows an overall fair agreement. The SWS estimates are assessed against satellite precipitation data and in situ river discharge and, in general, a relatively fair agreement is found between the three hydrological variables at the basin and sub-basin scales (linear correlation coefficient >0.5). We further characterize the spatial distribution of the major drought that occurred across the basin at the end of 2005 and in early 2006. The SWS estimates clearly reveal the widespread spatial distribution of this severe event (∼40 % deficit as compared to their long-term average), in accordance with the large negative anomaly observed in precipitation over that period. This new SWS long-term dataset over the Congo River basin is an unprecedented new source of information for improving our comprehension of hydrological and biogeochemical cycles in the basin. As the datasets used in our study are available globally, our study opens opportunities to further develop satellite-derived SWS estimates at the global scale. The dataset of the CRB's SWS and the related Python code to run the reproducibility of the hypsometric curve approach dataset of SWS are respectively available for download at https://doi.org/10.5281/zenodo. 7299823 and https://doi.org/10.5281/zenodo.8011607 (Kitambo et al., 2022b, 2023).

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22

Chatelard, Patrick y Laurent Laborde. "ASTEC V2.2 code validation: Illustrative results and main outcomes". Nuclear Engineering and Design 413 (noviembre de 2023): 112547. http://dx.doi.org/10.1016/j.nucengdes.2023.112547.

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23

Lacerda, Benício de Morais y Alex Gomes Pereira. "NUMERICAL ANALYSIS OF STRUCTURAL ELEMENTS BETWEEN 3D CAD SOLIDWORKS AND CODE_ASTER". International Journal of Research -GRANTHAALAYAH 7, n.º 10 (4 de julio de 2020): 458–70. http://dx.doi.org/10.29121/granthaalayah.v7.i10.2019.542.

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This study aimed to investigate numerically the validation of the use of the free license program Code_ Aster, with numerical results of the SolidWorks program. For this, four metal elements were modeled, all of them subjected to the tensile stress, they are: a cylindrical bar, two plates with a hole and a metal console. The objective is to validate the use of a free program for analysis of structural elements in engineering office projects and institutional research to verify if the results obtained from the free program show significant differences in the numerical application of a commercial program. All programs have in their design of analysis the use of the finite element method (FEM). The finite element method (FEM) consists to divide a continuous object into a finite number of parts. This allows a complex problem to be transformed into a set of simple problems (finite element) in addition to solving a set of finite elements by approximations with good precision of the results and to model the problem in a real physical way. It was observed that the numerical results between the SolidWorks program and the free program Code_ Aster were close with differences of less than 5%, which indicates the reliability of the use of Code_ Aster for numerical analyzes of structural elements of engineering projects and also in institutional research.

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24

Chatelard, P., N. Reinke, A. Ezzidi, V. Lombard, M. Barnak, G. Lajtha, J. Slaby, M. Constantin y P. Majumdar. "Synthesis of the ASTEC integral code activities in SARNET – Focus on ASTEC V2 plant applications". Annals of Nuclear Energy 74 (diciembre de 2014): 224–42. http://dx.doi.org/10.1016/j.anucene.2014.05.010.

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25

Bujan, A., L. Ammirabile, A. Bieliauskas y B. Toth. "ASTEC V1.3 code SOPHAEROS module validation using the STORM experiments". Progress in Nuclear Energy 52, n.º 8 (noviembre de 2010): 777–88. http://dx.doi.org/10.1016/j.pnucene.2010.05.004.

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26

Ammirabile, L., A. Bujan y M. Sangiorgi. "PWR Medium Break LOCA source term analysis using ASTEC code". Progress in Nuclear Energy 81 (mayo de 2015): 30–42. http://dx.doi.org/10.1016/j.pnucene.2015.01.001.

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27

Radu, Gabriela y Ilie Prisecaru. "Applications of ASTEC integral code on a generic CANDU 6". Nuclear Engineering and Design 286 (mayo de 2015): 237–45. http://dx.doi.org/10.1016/j.nucengdes.2015.02.015.

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28

Van Dorsselaere, J. P., P. Chatelard, M. Cranga, G. Guillard, N. Trégourès, L. Bosland, G. Brillant et al. "Validation Status of the ASTEC Integral Code for Severe Accident Simulation". Nuclear Technology 170, n.º 3 (junio de 2010): 397–415. http://dx.doi.org/10.13182/nt10-a10326.

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29

Cantrel, L., F. Cousin, L. Bosland, K. Chevalier-Jabet y C. Marchetto. "ASTEC V2 severe accident integral code: Fission product modelling and validation". Nuclear Engineering and Design 272 (junio de 2014): 195–206. http://dx.doi.org/10.1016/j.nucengdes.2014.01.011.

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30

Abdel-Latif, S. H. "Severe accident simulation for VVER-1000 reactor using ASTEC-V2.1.1.3". Kerntechnik 86, n.º 6 (1 de diciembre de 2021): 454–69. http://dx.doi.org/10.1515/kern-2021-0017.

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Abstract The station black-out (SBO) is one of the main accident sequences to be considered in the field of severe accident research. To evaluate a nuclear power plant’s behavior in the context of this accident, the integral ASTEC-V2.1.1.3 code “Accident Source Term Evaluation Code” covers sequences of SBO accidents that may lead to a severe accident. The aim of this work is to discuss the modelling principles for the core melting and in-vessel melt relocation phenomena of the VVER-1000 reactor. The scenario of SBO is simulated by ASTEC code using its basic modules. Then, the simulation is performed again by the same code after adding and activating the modules; ISODOP, DOSE, CORIUM, and RCSMESH to simulate the ex-vessel melt. The results of the two simulations are compared. As a result of SBO, the active safety systems are not available and have not been able to perform their safety functions that maintain the safety requirements to ensure a secure operation of the nuclear power plant. As a result, the safety requirements will be violated causing the core to heat-up. Moreover potential core degradation will occur. The present study focuses on the reactor pressure vessel failure and relocation of corium into the containment. It also discusses the transfer of Fission Products (FPs) from the reactor to the containment, the time for core heat-up, hydrogen production and the amount of corium at the lower plenum reactor pressure vessel is determined.

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31

Perez-Martin, Sara, Giacomino Bandini, Vaidas Matuzas, Michael Buck y Nathalie Girault. "ICONE23-2041 FIRST ANALYSIS OF AGS0, LT2 AND E9 CABRI TESTS WITH THE NEW SFR SAFETY CODE ASTEC-NA". Proceedings of the International Conference on Nuclear Engineering (ICONE) 2015.23 (2015): _ICONE23–2—_ICONE23–2. http://dx.doi.org/10.1299/jsmeicone.2015.23._icone23-2_17.

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32

Kačegavičius, Tomas y Egidijus Urbonavičius. "Modelling of Ingress of Coolant Event into Vacuum Experiments with ASTEC Code". Journal of Fusion Energy 34, n.º 2 (13 de noviembre de 2014): 320–25. http://dx.doi.org/10.1007/s10894-014-9804-4.

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33

Duval, Antoine, Herman Ram, Marjolaine Viret, Emily Wisnosky, Howard L. Jacobs y Mike Morgan. "The World Anti-Doping Code 2015: ASSER International Sports Law Blog symposium". International Sports Law Journal 16, n.º 1-2 (10 de junio de 2016): 99–117. http://dx.doi.org/10.1007/s40318-016-0097-9.

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34

Nowack, H., P. Chatelard, L. Chailan, St Hermsmeyer, V. Sanchez y L. Herranz. "CESAM – Code for European severe accident management, EURATOM project on ASTEC improvement". Annals of Nuclear Energy 116 (junio de 2018): 128–36. http://dx.doi.org/10.1016/j.anucene.2018.02.021.

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35

Maccari, Pietro, Giuseppe Agnello, Fulvio Mascari y Stefano Ederli. "Analysis of BDBA sequences in a generic IRIS reactor using ASTEC code". Annals of Nuclear Energy 182 (marzo de 2023): 109611. http://dx.doi.org/10.1016/j.anucene.2022.109611.

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36

Séropian, C., M. Barrachin, J. P. Van Dorsselaere y D. Vola. "Adaptation of the ASTEC code system to accident scenarios in fusion installations". Fusion Engineering and Design 88, n.º 9-10 (octubre de 2013): 2698–703. http://dx.doi.org/10.1016/j.fusengdes.2013.02.058.

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37

Jo, Eun-Ah, Sujeong Seong, Sanghyun Ahn, Hyejin Mo, In-Mok Jung, Hyo Kee Kim, Hyunmin Ko, Ahram Han, Sangil Min y Seung-Kee Min. "Validation of I71.3 code for ruptured abdominal aortic aneurysm in Korea: misplaced diagnosis in claims data". Annals of Surgical Treatment and Research 104, n.º 3 (2023): 170. http://dx.doi.org/10.4174/astr.2023.104.3.170.

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38

NARDI, GIANLUCA, GIOVANNI DELLACASA y MARCO DELLACASA. "On the type species of Geophilus Gistel, 1834 (Coleoptera: Scarabaeidae: Aphodiinae)". Zootaxa 4461, n.º 1 (20 de agosto de 2018): 83. http://dx.doi.org/10.11646/zootaxa.4461.1.6.

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Geophilus Gistel, 1834 (Insecta: Coleoptera: Scarabaeidae: Aphodiinae) is invalid being a junior homonym of Geophilus Leach, 1814 (Myriapoda: Chilopoda: Geophilomorpha: Geophilidae) and of Geophilus Schönherr, 1823 (Insecta: Coleoptera: Curculionidae). Scarabaeus asper Fabricius, 1775 was recently designated as type species of Geophilus Gistel, 1834, making Geophilus a junior synonym of Psammodius Fallén, 1807 (Insecta: Coleoptera: Scarabaeidae: Aphodiinae: Psammodiini: Psammodiina). However, there is clear evidence that Scarabaeus asper Fabricius, 1775 sensu Gistel, 1834 is Ptinus germanus Linnaeus, 1767, currently Rhyssemus germanus (Linnaeus, 1767) (Insecta: Coleoptera: Scarabaeidae: Aphodiinae: Psammodiini: Rhyssemina). To resolve this issue, the type species of Geophilus Gistel, 1834 is here fixed (under Article 70.3.2 of the International Code of Zoological Nomenclature) as Ptinus germanus Linnaeus, 1767, misidentified as Scarabaeus asper Fabricius, 1775 in the original paper. Scarabaeus asper Fabricius, 1775 sensu Mulsant, 1842 (= Ptinus germanus Linnaeus, 1767) is the type species of Rhyssemus Mulsant, 1842, therefore Rhyssemus Mulsant, 1842 is a junior synonym of Geophilus Gistel, 1834 (new synonymy). Although it has priority, Geophilus Gistel, 1834 is a junior homonym and therefore invalid, so Rhyssemus Mulsant, 1842 remains the valid name of this taxon.

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39

Kljenak, Ivo, Maik Dapper, Jiří Dienstbier, Luis E. Herranz, Marco K. Koch y Joan Fontanet. "Thermal-hydraulic and aerosol containment phenomena modelling in ASTEC severe accident computer code". Nuclear Engineering and Design 240, n.º 3 (marzo de 2010): 656–67. http://dx.doi.org/10.1016/j.nucengdes.2009.12.002.

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40

Chatelard, P., N. Reinke, S. Arndt, S. Belon, L. Cantrel, L. Carenini, K. Chevalier-Jabet et al. "ASTEC V2 severe accident integral code main features, current V2.0 modelling status, perspectives". Nuclear Engineering and Design 272 (junio de 2014): 119–35. http://dx.doi.org/10.1016/j.nucengdes.2013.06.040.

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41

Brillant, G., C. Marchetto y W. Plumecocq. "Fission product release from nuclear fuel I. Physical modelling in the ASTEC code". Annals of Nuclear Energy 61 (noviembre de 2013): 88–95. http://dx.doi.org/10.1016/j.anucene.2013.03.022.

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42

TREGOURES, Nicolas, Giacomino BANDINI, Laurent FOUCHER, Joëlle FLEUROT y Paride MELONI. "Validation of CESAR Thermal-hydraulic Module of ASTEC V1.2 Code on BETHSY Experiments". Journal of Power and Energy Systems 2, n.º 1 (2008): 386–96. http://dx.doi.org/10.1299/jpes.2.386.

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43

Lonsdale, R. D. "The ASTEC Code: An Algorithm for Solving Thermal-Hydraulic Equations in Complex Geometries". Nuclear Science and Engineering 100, n.º 4 (diciembre de 1988): 385–92. http://dx.doi.org/10.13182/nse88-a23571.

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44

GRIGORISHIN, Sergey V. y Ekaterina V. NOVOKRESHCHENNYKH. "CODEX B 19A: STAGES OF LEGITIMATION OF THE MASORET BIBLE ANCIENT EXAMPLE". Tyumen State University Herald. Humanities Research. Humanitates 7, n.º 1 (2021): 20–42. http://dx.doi.org/10.21684/2411-197x-2021-7-1-20-42.

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This article examines the cultural and historical circumstances of the appearance and introduction into the scientific circulation of the oldest manuscript code of the Hebrew Bible — the Leningrad Code B 19A. The authors of the article make an attempt to restore the contextual connections of the Code with Jewish philosophy and biblical textology. The concept of the research is built on the basis of genealogical analysis, which opened up the opportunity to first analyze the stages of legitimation of Codex B 19A that are closest to the present, and then move into the depth of chronology, right up to the moment of creation of the studied text. The result of the study was the identification and explication of internal links between the Codex B 19A, Masoretic schools, Rabbanites, Karaites and, finally, medieval critics of the biblical text. The research methodology is based on the principles of philosophical hermeneutics, the comparative historical approach of the genealogical method as applied to textual criticism. Revealing the cause-and-effect relationship in the legitimization of the Masoretic Bible showed that the need to create a single standard for the sacred text arose already by the middle of the 8th century, the time of the emergence of the Karaite movement. The refusal of the Karaites to submit to the authority of classical rabbinical literature led to a rethinking of the biblical text. Together with the status of the main sacred book, the Bible turned out to be a text around which philological, philosophical and theological discussions became possible. Awareness of the fact that the biblical text has different interpretations led the Rabbanites and Karaites to the conclusion that it was necessary to create a philological standard for the Bible. For this reason, the authority of the Masoretes as specialists in the vocalization of the text, the direct creators of the vocalization system, has sharply increased. The Ben Asher family of Tiberias emerged as the main Masoretic school, and its last representative, Aaron Ben Asher, became the most authoritative Masoretic. Aaron Ben Asher owns the Masorah system introduced in the Aleppo Codex and copied in the Leningrad Codex B 19A. Maimonides was the first among Jewish philosophers to appreciate the textual achievements of Aaron Ben Asher, which significantly raised the authority of the Masoret in rabbinic and Karaite intellectual circles.

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45

Kaliatka, Algirdas, Viktor Ognerubov, Virginijus Vileiniškis y Eugenijus Ušpuras. "Analysis of the Processes in Spent Fuel Pools in Case of Loss of Heat Removal due to Water Leakage". Science and Technology of Nuclear Installations 2013 (2013): 1–11. http://dx.doi.org/10.1155/2013/598975.

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The safe storage of spent fuel assemblies in the spent fuel pools is very important. These facilities are not covered by leaktight containment; thus, the consequences of overheating and melting of fuel in the spent fuel pools can be very severe. On the other hand, due to low decay heat of fuel assemblies, the processes in pools are slow in comparison with processes in reactor core during LOCA accident. Thus, the accident management measures play a very important role in case of some accidents in spent fuel pools. This paper presents the analysis of possible consequences of fuel overheating due to leakage of water from spent fuel pool. Also, the accident mitigation measure, the late injection of water was evaluated. The analysis was performed for the Ignalina NPP Unit 2 spent fuel pool, using system thermal hydraulic code for severe accident analysis ATHLET-CD. The phenomena, taking place during such accident, are discussed. Also, benchmarking of results of the same accident calculation using ASTEC and RELAP/SCDAPSIM codes is presented here.

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46

Vileiniskis, V. y A. Kaliatka. "Best estimate analysis of PHEBUS FPT1 experiment bundle phase using ASTEC code ICARE module". Kerntechnik 76, n.º 4 (agosto de 2011): 254–60. http://dx.doi.org/10.3139/124.110158.

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47

Maccari, Pietro, Fulvio Mascari, Stefano Ederli, Paride Meloni y Sandro Manservisi. "ASTEC code DBA analysis of a passive mitigation strategy on a generic IRIS SMR". Annals of Nuclear Energy 156 (junio de 2021): 108194. http://dx.doi.org/10.1016/j.anucene.2021.108194.

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48

Bonneville, H. y A. Luciani. "Simulation of the core degradation phase of the Fukushima accidents using the ASTEC code". Nuclear Engineering and Design 272 (junio de 2014): 261–72. http://dx.doi.org/10.1016/j.nucengdes.2013.06.043.

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49

Atanasova, B. P., A. E. Stefanova y P. P. Groudev. "VVER 1000 SBO calculations with pressuriser relief valve stuck open with ASTEC computer code". Annals of Nuclear Energy 46 (agosto de 2012): 121–27. http://dx.doi.org/10.1016/j.anucene.2011.12.024.

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50

Smith, B. L. y T. V. Dury. "On the use of heat transfer correlations for internal surfaces in the ASTEC code". Applied Mathematical Modelling 20, n.º 3 (marzo de 1996): 187–99. http://dx.doi.org/10.1016/0307-904x(95)00152-a.

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