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MECOM 2025, XLI Congreso Argentino de Mecánica Computacional

Nov 11 – 14, 2025
Buenos Aires, Argentina
America/Argentina/Buenos_Aires timezone

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Session

Parallel Session M4b-316 | Nuclear Reactors Engineering

Nov 14, 2025, 11:30 AM
A316 (FIUBA, 3rd floor)

A316

FIUBA, 3rd floor

Description

S2512 | Part 3 / 3
Nuclear Reactors Engineering
Ingeniería de Reactores Nucleares

Chairs | Directores:
Santiago Corzo, Juan Ramos Nervi

Presentation materials

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  1. 203. S2512-ID-8397-Digital twin model of a Steam Generator to support Reliability-Centered Maintenance in the Nuclear Industry
    Dávid Huri (University of Debrecen, Hungary), László Molnár (University of Debrecen, Hungary), Tamás Mankovits (University of Debrecen, Hungary)
    11/14/25, 11:30 AM

    The research aims to develop a procedure, which can be used in the design and operation of nuclear power plants, which can predict the change in state of dangerous system components under specific load conditions. Fatigue life calculation methods available with simulation technology were applied to establish the procedure, and their outputs were incorporated into the output variables of a...

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  2. 201. S2512-ID-8391-Application of additive manufacturing technology in nuclear power plant maintenance with special focus on mechanical properties
    Levente Czégé (University of Debrecen, Hungary), Daniel Nemes (University of Debrecen, Hungary), Dávid Huri (University of Debrecen, Hungary), Tamás Mankovits (University of Debrecen, Hungary)
    11/14/25, 11:50 AM

    The objective of the study is to examine the application of additive manufacturing technology in nuclear power plant maintenance, with specific focus on the mechanical properties of the 3D printed parts. The development of additive manufacturing technologies offers a novel opportunity to enhance the efficiency of maintenance processes enabling the rapid, on-site production of required spare...

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  3. 202. S2512-ID-8392-Fatigue Life Analysis of a Steam Generator used for Nuclear Power Plants using Sub-modeling Technique
    Tamás Mankovits (University of Debrecen, Hungary), László Molnár (University of Debrecen, Hungary), Dávid Huri (University of Debrecen, Hungary)
    11/14/25, 12:10 PM

    Over the past two decades, several crack failures have been detected in the weld area between the collector and the steam generator tank, requiring repair or replacement of the tank in several cases. Given the high economic risk of replacing a cracked steam generator, it may be advisable to develop an intelligent maintenance system that incorporates computer tools. This would enable the...

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  4. 308. S2512-ID-8290-Modelado del SAG en canales combustibles de la Central Nuclear Embalse
    Braian A. Desía (NA-SA, Nucleoelectrica Argentina S.A., Prov. Buenos Aires, Argentina), Juan Ramos Nervi (NA-SA, Nucleoelectrica Argentina S.A., Prov. Buenos Aires, Argentina), Ezequiel M. Fernandez (NA-SA, Nucleoelectrica Argentina S.A., Prov. Buenos Aires, Argentina)
    11/14/25, 12:30 PM

    Un aspecto esencial en el manejo de la vida útil de los canales combustibles en reactores del tipo CANDU es la prevención del contacto entre el Tubo de Presión (PT) y el Tubo de Calandria (CT). En condiciones normales de operación, dicho contacto puede ocurrir como resultado del creep por irradiación. Por lo tanto, el desarrollo de modelos computacionales que permitan predecir la respuesta del...

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