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The authors acknowledge ENUSA Industrias Avanzadas S.A., S.M.E for the financial and technical support of this research project.
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Benavides, JulioAutor o CoautorJimenez, GonzaloAutor (correspondencia)Lopez, SantiagoAutor o CoautorModeling and results of the dry cask simulator (DCS) with STAR-CCM
Publicado en:Nuclear Engineering And Design. 369 (110820): - 2020-12-01 369(110820), DOI: 10.1016/j.nucengdes.2020.110820
Autores: Benavides, Julio; Jimenez, Gonzalo; Lopez, Santiago; Galban, Marta; Lloret, Miriam;
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Resumen
To understand the behavior of commercial nuclear fuel during its storage phase in spent fuel dry storage casks, simulations are necessary and to validate the simulation models, full-scale experiments are required. Therefore, an experimental facility called the dry cask simulator (DCS) was built in Sandia National Laboratories with the purpose of producing validation-quality data that can be used to test the accuracy of the modeling used to determine cladding temperatures in modern vertical dry casks. The DCS has been created under the framework of the Extended Storage Collaboration Programme (ESCP), coordinated by EPRI. The ultimate goal of the DCS was to study the thermal-hydraulic response of a single boiling water reactor (BWR) fuel assembly under variety of heat loads, internal vessel pressures, and external configurations. In this article, the simulations conducted by ENUSA Industrias Avanzadas S.A., S.M.E and UPM (Universidad Politecnica de Madrid, Spain) using STAR-CCM+ are validated against the experiments conducted at Sandia National Laboratories. In order to validate the simulation models several sensitivity analyses have been performed: a grid convergence index to estimate the discretization error in the simulations, a turbulence model sensitivity for the inner part of the cask, and three different approaches to model the fuel assembly: Case 1 (model with no spacers and no bottom tie plate), Case 2 (model with spacers and no bottom tie plate and Case 3 (model with spacers and bottom tie plate). Additionally, a thermal-hydraulic analysis is also presented, not only to explain the difference between the three ways to model the fuel assembly, but also to obtain a better understanding of the behavior of the dry cask according to pressure and heat output changes. Among the three cases, the simplest model (Case 1) has proven to obtain the most accurate results, being able to predict the temperature distribution in the fuel assembly and the air mass flow compared to the experiment measurements for all four cases of study. Meanwhile, the two other cases have shown that for steady state solutions the spacers and the bottom tie plate are not necessary and can introduce unwanted errors. Nonetheless, all cases have provided insight into the behavior of a dry storage cask system under different conditions showing the different heat transfer mechanisms interactions.
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Indicios de calidad
Impacto bibliométrico. Análisis de la aportación y canal de difusión
El trabajo ha sido publicado en la revista Nuclear Engineering And Design debido a la progresión y el buen impacto que ha alcanzado en los últimos años, según la agencia Scopus (SJR), se ha convertido en una referencia en su campo. En el año de publicación del trabajo, 2020, se encontraba en la posición , consiguiendo con ello situarse como revista Q1 (Primer Cuartil), en la categoría Safety, Risk, Reliability and Quality. Destacable, igualmente, el hecho de que la Revista está posicionada por encima del Percentil 90.
2025-07-21:
- WoS: 2
- Scopus: 4
Impacto y visibilidad social
Análisis de liderazgo de los autores institucionales
Este trabajo se ha realizado con colaboración internacional, concretamente con investigadores de: United States of America.
Existe un liderazgo significativo ya que algunos de los autores pertenecientes a la institución aparecen como primer o último firmante, se puede apreciar en el detalle: Primer Autor (BENAVIDES RODRIGUEZ, JULIO) .
el autor responsable de establecer las labores de correspondencia ha sido JIMENEZ VARAS, GONZALO.