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dc.contributor.author
Magni, María Celeste  
dc.contributor.author
Marcel, Christian Pablo  
dc.contributor.author
Delmastro, Dario Fabian  
dc.date.available
2024-05-07T12:42:23Z  
dc.date.issued
2022-04  
dc.identifier.citation
Magni, María Celeste; Marcel, Christian Pablo; Delmastro, Dario Fabian; Thermal-hydraulic stability investigations of once through helically coiled steam generators for SMR applications; Elsevier Science SA; Nuclear Engineering and Design; 396; 4-2022; 1-16  
dc.identifier.issn
0029-5493  
dc.identifier.uri
http://hdl.handle.net/11336/234725  
dc.description.abstract
Once-through steam generators with helically-coiled tubes (OTSG-HC) are susceptible to density wave instability phenomena. In order to investigate the stability performance of the CAREM-25 OTSG-HC, a new stability model is presented. Such a model being linear and strictly non-diffusive is able to represent arbitrary heat flux profiles, which is essential to study realistic cases. The OTSG-HC tubes are modeled by three different regions representing the liquid zone, the boiling zone, and the superheated vapor zone. Moreover, the coolant from the primary side is coupled with a model representing the phenomena present in CAREM-25. A convenient parameter space for stability representation is found and used to characterize the CAREM-25 OTSG-HC stability performance.In this work, special attention is paid to the calculation of the friction pressure losses in the coolant flowing through the helically coiled tubes. For this reason, a best estimate correlation is implemented and used in the model together with a sophisticated axial power profile model which allows representing realistic boundary conditions. As a result, it is confirmed the crucial importance of correctly representing the axial power profile transferred in the helically coiled tubes. In addition, it is found the commonly used uniform axial power profile leads to non-conservative stability predictions particularly at low power conditions. The latter is explained by the underestimation of the boiling and superheating lengths, which is proved to have a destabilizing effect.Stability maps are presented in terms of the transferred power and the primary coolant operational pressure, i.e. Qsg-Ppri plane. It is observed that when modeling realistic power profiles, the less stable operational condition of the OTSG-HC is found at very low powers, for all analyzed range of primary pressures. In addition, a weak stability dependence of the OTSG-HC with the pressure of the primary side is observed. Finally, the system is stabilized in the region of interest and its stability performance quantified.  
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
Density wave oscillations  
dc.subject
Small Modular Reactors  
dc.subject
Once Trough Steam Generator  
dc.subject
Helically coiled tubes  
dc.subject.classification
Ingeniería Nuclear  
dc.subject.classification
Ingeniería Mecánica  
dc.subject.classification
INGENIERÍAS Y TECNOLOGÍAS  
dc.title
Thermal-hydraulic stability investigations of once through helically coiled steam generators for SMR applications  
dc.type
info:eu-repo/semantics/article  
dc.type
info:ar-repo/semantics/artículo  
dc.type
info:eu-repo/semantics/publishedVersion  
dc.date.updated
2024-05-07T10:41:23Z  
dc.journal.volume
396  
dc.journal.pagination
1-16  
dc.journal.pais
Países Bajos  
dc.journal.ciudad
Amsterdam  
dc.description.fil
Fil: Magni, María Celeste. Comisión Nacional de Energía Atómica. Gerencia del Área de Energía Nuclear. Instituto Balseiro; Argentina  
dc.description.fil
Fil: Marcel, Christian Pablo. Consejo Nacional de Investigaciones Científicas y Técnicas; Argentina. Comisión Nacional de Energía Atómica. Gerencia del Área de Energía Nuclear. Instituto Balseiro; Argentina  
dc.description.fil
Fil: Delmastro, Dario Fabian. Comisión Nacional de Energía Atómica. Gerencia del Área de Energía Nuclear. Instituto Balseiro; Argentina  
dc.journal.title
Nuclear Engineering and Design  
dc.relation.alternativeid
info:eu-repo/semantics/altIdentifier/url/https://www.sciencedirect.com/science/article/pii/S0029549322002412  
dc.relation.alternativeid
info:eu-repo/semantics/altIdentifier/doi/http://dx.doi.org/10.1016/j.nucengdes.2022.111887