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Buenos Aires, Argentina

Gaute F.,Nucleoelectrica Argentina SA
International Journal of Low Radiation | Year: 2011

The main purpose of this paper is to explain the Radiological Assessment Programme implemented by Nucleoeléctrica Argentina SA (NASA) in the Atucha I NPP and Atucha II NPP sites. Atucha I NPP reached its first criticality in 1974, while Atucha II NPP will start its commercial operation in the last quarter of 2011. The Radiological Assessment Programme verifies the compliance of the basic safety standards with reference to the radiation exposure of the population in the surrounding area and the environmental impact searching for continuous improvement, as a result of applying the ALARA philosophy. The reference levels are calculated considering a theoretical dose of 0.05 mSv/year for the critical group. This value is considered for the discharge limits for Atucha I NPP (Ki) in the Operations Licence in force, and those limits comprise all the radionuclides established in the Argentine Regulatory Authority Requirements. Copyright © 2011 Inderscience Enterprises Ltd. Source


Dauria F.,University of Pisa | Mazzantini O.,Nucleoelectrica Argentina SA
Science and Technology of Nuclear Installations | Year: 2011

Within the licensing process of the KWU Atucha II PHWR (Pressurized Heavy Water Reactor), the BEPU (Best Estimate Plus Uncertainty) approach has been selected for issuing of the Chapter 15 on FSAR (Final Safety Analysis Report). The key steps of the entire process are basically two: (a) the selection of PIE (Postulated Initiating Events) and (b) the analysis by best estimate models supported by uncertainty evaluation. Otherwise, key elements of the approach are (1) availability of qualified computational tools including suitable uncertainty method, (2) demonstration of quality, and (3) acceptability and endorsement by the licensing authority. The effort of issuing Chapter 15 is terminated at the time of issuing of the present paper, and the safety margins available for the operation of the concerned NPP (Nuclear Power Plant) have been quantified. © 2011 Francesco DAuria and Oscar Mazzantini. Source


Katchadjian P.,Comision Nacional de la Energia Atomica | Desimone C.,Comision Nacional de la Energia Atomica | Garcia A.,Comision Nacional de la Energia Atomica | Schroeter F.,Nucleoelectrica Argentina SA
AIP Conference Proceedings | Year: 2012

In this paper the applications, detailed in previous works, of ultrasonic transducers with the addition of axicon lenses are extended. Axicon lenses were manufactured to generate an angular refracted beam in order to study defectology in welds and other components. To achieve greater depth of focus while maintaining a relationship between focus depth and near field (F/N) less than 0.4, larger diameter transducers were used. Furthermore, its effect on the focus diameter (dF) was also analyzed. For different combinations of lens-transducer, diagrams of axial and transverse sound pressure distribution were obtained. At last, several practical applications are shown where it is possible to exploit the advantages that these transducers offer; for example: sizing of shallow cracks, high resolution corrosion mapping simulation, etc. © 2012 American Institute of Physics. Source


Idiart M.I.,National University of La Plata | Idiart M.I.,CONICET | Ramos Nervi J.E.,National University of La Plata | Ramos Nervi J.E.,Nucleoelectrica Argentina SA
Comptes Rendus - Mecanique | Year: 2014

A linear-comparison homogenization technique and its relaxed version are used to compute bounds of the Hashin-Shtrikman and the self-consistent types for the hydrostatic strength of ideally plastic voided polycrystals. Closed-form analytical results are derived for isotropic aggregates of various cubic symmetries (fcc, bcc, ionic). The impact of the variational relaxation on the bounds is found to be significantly larger than that previously observed in fully dense polycrystals. So much so that, quite surprisingly, relaxed self-consistent bounds are found to be weaker than non-relaxed Hashin-Shtrikman bounds in some of the material systems considered. © 2013 Académie des sciences. Source


Adorni M.,University of Pisa | Del Nevo A.,University of Pisa | D'Auria F.,University of Pisa | Mazzantini O.,Nucleoelectrica Argentina SA
International Conference on Nuclear Engineering, Proceedings, ICONE | Year: 2010

Depending on the specific event scenario and on the purpose of the analysis, it might be required the availability of calculation methods that are not implemented in the standard system thermal hydraulic codes. This may imply the use of a dedicated fuel rod thermo-mechanical computer code. This paper provides an outline of the methodology for the analysis of the 2A LB-LOCA accident in Atucha-2 NPP and describes the procedure adopted for the use of the fuel rod thermomechanical code. The methodology implies the application of best estimate thermal-hydraulic, neutron physics and fuel pin performance computer codes, with the objective to verify the compliance with the specific acceptance criteria. The fuel pin performance code is applied with the main objective to evaluate the extent of cladding failures during the transient. The procedure consists of a deterministic calculation by the fuel performance code of each individual fuel rod during its lifetime and in the subsequent LB-LOCA transient calculations. The boundary and initial conditions (e.g. pin power axial profiles) are provided by core physics and three dimensional neutron kinetic coupled thermal-hydraulic system codes (RELAP5-3D©) calculations. The procedure is completed by the sensitivity calculations and the application of the probabilistic method, with the aim of a better understanding of the uncertainties involved and their technological consequences on the behavior of the fuel rods, not addressed in the current paper. Copyright © 2010 by ASME. Source

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