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A novel computational platform for the propagation of nuclear data uncertainties through the fuel cycle code ANICCA
Hernández-Solís, A.; Merino-Rodríguez, Iván; Fiorito, Luca; Van den Eynde, G. (2021)This paper presents the first results of a computational platform dedicated to the propagation of nuclear data covariances, all the way to fuel cycle scenario observables. Such platform, based on in-house codes developed ...
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ANICCA, a computational tool for simulating nuclear fuel cycles
Merino-Rodríguez, Iván; Hernández-García, Ruber; Hernández-Solís, A. (2020)Fuel cycle simulation codes are tools developed and used worldwide to answer the many questions that arise in relation to the development or deployment of nuclear technology for electricity generation. In this context, ...
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Deep learning models as an approach to nuclear fuel irradiation processes in pressurized water reactors
Casas Molina, Víctor J.; Hernández-Solís, A.; Merino-Rodríguez, Iván; Romojaro Otero, Pablo (2022)ANICCA is the nuclear fuel cycle code developed by the Belgian Nuclear Research Centre (SCK CEN). Nuclear Fuel Cycle codes are of special importance for the assessment of the scenarios and the study of nuclear reactor fleet ...
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Environmental assessment of energy scenarios for a low-carbon electrical network in Chile
Merino-Rodríguez, Iván; Herrera, Israel; Valdés-Riquelme, Hugo (2019)Nowadays, establishing clean energy sources is an undeniable need for all territories to reconcile energy and competitiveness objectives with those of security and sustainability. This article shows the main advantages of ...
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Quantification of the differences introduced by nuclear fuel cycle simulators in advanced scenario studies
Skarbeli, A.V.; Merino-Rodríguez, Iván; Álvarez-Velarde, F.; Hernández-Solís, A.; Van den Eynde, G. (2020)Uncertainty propagation and quantification, when applied to the field of nuclear fuel cycle scenario studies, usually only considers a set of easily quantifiable input parameters, leaving out the effects of the modelling ...
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The nuclear fuel cycle code ANICCA: Verification and a case study for the phase out of belgian nuclear power with minor actinide transmutation
Merino-Rodríguez, Iván; Hernández-Solís, A.; Messaoudi, N.; Van den Eynde, G. (2020)The Nuclear Fuel Cycle Code “ANICCA” has been developed by SCK•CEN to answer particular questions about the Belgian nuclear fleet. However, the wide range of capabilities of the code make it also useful for international ...
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What hides Chile’s electricity mix data: a data science perspective
Soto, Javier; Moore, Michaol; López-Cortés, Xaviera A.; Hernández-García, Ruber; Merino-Rodríguez, Iván (2022)In the context of decarbonization and fossil fuel independence, Chile has a great task ahead. The most relevant is to become carbon neutral by 2050 by replacing fossil fuels with clean energy sources, where, besides ...