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dc.contributor.author
Umezu, Ivan K.  
dc.contributor.author
Godino, Dario Martin  
dc.contributor.author
Ramajo, Damian Enrique  
dc.contributor.author
Pereira, Claubia  
dc.contributor.author
Costa, Antonella L.  
dc.date.available
2025-03-31T13:23:49Z  
dc.date.issued
2024-12  
dc.identifier.citation
Umezu, Ivan K.; Godino, Dario Martin; Ramajo, Damian Enrique; Pereira, Claubia; Costa, Antonella L.; CFD modeling methods applied to a lead-cooled fast reactor: A parametric study on conjugate heat transfer and thermal boundary conditions; Elsevier Science SA; Nuclear Engineering and Design; 429; 12-2024; 1-18  
dc.identifier.issn
0029-5493  
dc.identifier.uri
http://hdl.handle.net/11336/257678  
dc.description.abstract
Given the ever-increasing global demand for energy and the need to reduce greenhouse gas emissions, small modular reactors (SMRs), have emerged as potential options for increasing the contribution of nuclear energy, offering lower costs and faster deployment compared to traditional nuclear projects. In the context of this technological development, safety studies have become a priority, particularly for licensing new-generation systems such as metal-cooled fast reactors. This work models the steady-state operation of the lead-cooled SMRSEALER Arctic using Computational Fluid Dynamics. The entire primary circuit of the SEALER is modeled; the core is represented as a combination of porous media and heat sources, the pumps are represented as recirculating boundary conditions to account for momentum sources, and the steam generators are representedas porous media coupled with a temperature-dependent heat sink function. The main objective of this study is to simulate the SEALER under steady-state condition, while also accounting for the effects of heat conduction through its solid regions, and heat losses on the reactor vessel wall to the environment. For the former, the reactor is modeled with and without conductive solids and surfaces, using a conjugate heat transfer model. For the latter, natural convection and radiation heat transfer considerations are included as boundary conditions, and a parametric study is carried out with a range of external temperatures, and their effects on fuel and coolant temperatures are also discussed. Despite significant differences in local temperatures near the vesselwalls, the impact on the peak fuel temperature and the average coolant temperature was less noticeable. Ultimately, the general operating parameters of the steady-state reactor design were verified, which is thefirst step before using the current model to evaluate fast transients and postulated events, where the thermal inertia of the solids and additional heat losses could play a crucial role on determining the system’s responseto rapid temperature changes.  
dc.format
application/pdf  
dc.language.iso
eng  
dc.publisher
Elsevier Science SA  
dc.rights
info:eu-repo/semantics/restrictedAccess  
dc.rights.uri
https://creativecommons.org/licenses/by-nc-sa/2.5/ar/  
dc.subject
CFD  
dc.subject
CHT  
dc.subject
Porous media  
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LFR  
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SMR  
dc.subject.classification
Ingeniería Nuclear  
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Ingeniería Mecánica  
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INGENIERÍAS Y TECNOLOGÍAS  
dc.title
CFD modeling methods applied to a lead-cooled fast reactor: A parametric study on conjugate heat transfer and thermal boundary conditions  
dc.type
info:eu-repo/semantics/article  
dc.type
info:ar-repo/semantics/artículo  
dc.type
info:eu-repo/semantics/publishedVersion  
dc.date.updated
2025-03-28T11:47:23Z  
dc.journal.volume
429  
dc.journal.pagination
1-18  
dc.journal.pais
Países Bajos  
dc.journal.ciudad
Amsterdam  
dc.description.fil
Fil: Umezu, Ivan K.. Universidade Federal de Minas Gerais; Brasil  
dc.description.fil
Fil: Godino, Dario Martin. Consejo Nacional de Investigaciones Científicas y Técnicas. Centro Científico Tecnológico Conicet - Santa Fe. Centro de Investigaciones en Métodos Computacionales. Universidad Nacional del Litoral. Centro de Investigaciones en Métodos Computacionales; Argentina  
dc.description.fil
Fil: Ramajo, Damian Enrique. Consejo Nacional de Investigaciones Científicas y Técnicas. Centro Científico Tecnológico Conicet - Santa Fe. Centro de Investigaciones en Métodos Computacionales. Universidad Nacional del Litoral. Centro de Investigaciones en Métodos Computacionales; Argentina  
dc.description.fil
Fil: Pereira, Claubia. Universidade Federal de Minas Gerais; Brasil  
dc.description.fil
Fil: Costa, Antonella L.. Universidade Federal de Minas Gerais; Brasil  
dc.journal.title
Nuclear Engineering and Design  
dc.relation.alternativeid
info:eu-repo/semantics/altIdentifier/url/https://linkinghub.elsevier.com/retrieve/pii/S0029549324007490  
dc.relation.alternativeid
info:eu-repo/semantics/altIdentifier/doi/http://dx.doi.org/10.1016/j.nucengdes.2024.113649