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1 to 42 of 42 results
  • Thermal and fluid dynamic study of cold storage

     Ruiz Mansilla, Rafael; Montserrat Jorda, Jose; Quera Miro, Manuel; Mas de Les Valls Ortiz, Elisabet; Ribe Torijano, Oscar
    Congreso Ibérico de Ciencias y Técnicas del Frío
    p. 179-188
    Presentation's date: 2014-06-20
    Presentation of work at congresses

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    In any cold storage, it is common that the air distribution system generates some heterogeneity in the temperatures inside. Depending on the type of the product, the tolerance can be taken in more or less close and, beyond it, a problem in the degradation of the genre can appear. For some products, such as laboratory or pharmaceutical products, the problem can be critical because, unlike foodstuffs, such a degradation is difficult to appreciate immediately. The present study uses OpenFOAM to simulate the temperature and velocity fields in the storage areas and in a cold chamber for storing these products, in order to analyse posible hot spots or deviation from the optimal storage conditions, and proposes applicable design alternatives in the supply and return air system to correct the problem. Subsequently, the results of these simulations are compared with the experimental values measured on-site through the monitoring system.

  • Fluidodinámica computacional y sus aplicaciones en la industria nuclear

     Aldama, Jorge; Batet Miracle, Lluis; Chiva, Sergio; Martín-Fuertes, Francisco; Mas de Les Valls Ortiz, Elisabet; Miró, Rafael
    Date: 2014-03
    Report

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  • Tritium permeation analysis in liquid metal flows with helium bubbles as applied to liquid metal breeding blankets

     Mas de Les Valls Ortiz, Elisabet; Batet Miracle, Lluis; Sedano Miguel, Luis Angel
    International Symposium on Fusion Nuclear Technology
    p. 32
    Presentation's date: 2013-09-17
    Presentation of work at congresses

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  • Modelado de un ciclo de potencia de CO2 supercrítico para reactores de fusión utilizando RELAP5-3D

     Batet Miracle, Lluis; Álvarez Fernández, Josep Maria; Mas de Les Valls Ortiz, Elisabet; Pérez, Marina; Martínez Quiroga, Víctor Manuel; Reventos Puigjaner, Francesc-josep; Sedano Miguel, Luis Angel
    Reunión Anual de la Sociedad Nuclear Española
    p. 1-13
    Presentation's date: 2013-09-24
    Presentation of work at congresses

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    En el marco del programa español de Tecnología de Fusión TECNO_FUS se ha avanzado en la definición de sistemas para DEMO, entre ellos las unidades reproductoras de tritio y el ciclo de potencia. Para las primeras, se ha propuesto un diseño modular a doble refrigerante (PbLi-He). Para la conversión de potencia térmica a eléctrica se han investigado ciclos de CO2 supercrítico. Mediante el código de sistema RELAP5-3D© se ha simulado un ciclo de potencia de CO2 supercrítico con recompresión. El código está desarrollado por el Idaho National Laboratory de EEUU y ha sido aplicado tradicionalmente a la simulación de transitorios operacionales y accidentales de plantas nucleares de fisión. El objetivo del presente trabajo es estudiar las capacidades del código en el ámbito de la Tecnología de Fusión. En GET/T4F se ha desarrollado un modelo basado en la propuesta española de diseño TECNO_FUS. Dicho modelo incluye los sistemas de refrigerante primario (helio y PbLi), compresores, turbina e intercambiadores de calor (del tipo circuito impreso). Tras la puesta a punto del modelo se han ejecutado cálculos de estado estacionario para comprobar la adecuación de los parámetros seleccionados. Tras diseñar algunos sistemas de control se han ejecutado cálculos transitorios para demostrar las capacidades del código y del modelo. El estudio ha permitido aprovechar las capacidades de RELAP5-3D© in un ámbito donde existía poca experiencia en el uso del código, como es la simulación de los flujos de calor y de los ciclos termodinámicos que, en una futura planta de fusión, convertirán la potencia emitida por el plasma en energía mecánica como paso previo a la generación eléctrica. Como fruto de los análisis se destacan las fortalezas y debilidades de código y modelo, junto con conclusiones sobre su aplicabilidad a la Tecnología de Fusión.

  • Desarrollo e implementación de un modelo de permeación de tritio en presencia de burbujas de helio para envolturas tritigénicas de metal líquido

     Batet Miracle, Lluis; Mas de Les Valls Ortiz, Elisabet; Sedano Miguel, Luis Angel
    Reunión Anual de la Sociedad Nuclear Española
    p. 1-8
    Presentation's date: 2013-09-24
    Presentation of work at congresses

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    En los canales de metal líquido (ML) de las envolturas regeneradoras de un reactor de fusión la posibilidad de formación de burbujas de helio no es remota. La presencia de burbujas adheridas a la pared de los canales de ML afectaría a la transferencia de calor y a la permeación de tritio. Se han efectuado análisis de detalle (mallado fino), mediante OpenFOAM, del entorno de una burbuja adherida a la pared y se ha desarrollado un modelo para la permeación de tritio a través de una superficie de contacto ML-sólido parcialmente recubierta con burbujas de helio. El modelo desarrollado se ha implementado como ¿wall function¿ en OpenFOAM, se ha validado y se ha aplicado a un caso práctico, utilizando un mallado relativamente grueso. El modelo desarrollado reduce substancialmente la necesidad de potencia de cálculo respecto del cálculo detallado.

    En los canales de metal líquido (ML) de las envolturas regeneradoras de un reactor de fusión la posibilidad de formación de burbujas de helio no es remota. La presencia de burbujas adheridas a la pared de los canales de ML afectaría a la transferencia de calor y a la permeación de tritio. Se han efectuado análisis de detalle (mallado fino), mediante OpenFOAM, del entorno de una burbuja adherida a la pared y se ha desarrollado un modelo para la permeación de tritio a través de una superficie de contacto ML-sólido parcialmente recubierta con burbujas de helio. El modelo desarrollado se ha implementado como “wall function” en OpenFOAM, se ha validado y se ha aplicado a un caso práctico, utilizando un mallado relativamente grueso. El modelo desarrollado reduce substancialmente la necesidad de potencia de cálculo respecto del cálculo detallado.

  • Modelling of a supercritical CO2 power cycle for nuclear fusion reactors using RELAP5¿3D

     Batet Miracle, Lluis; Álvarez Fernández, Josep Maria; Mas de Les Valls Ortiz, Elisabet; Martínez Quiroga, Víctor Manuel; Perez Ferragut, Marina; Sedano Miguel, Luis Angel
    International Symposium on Fusion Nuclear Technology
    p. 458
    Presentation's date: 2013-09-19
    Presentation of work at congresses

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    Within the Spanish FT Program TECNO_FUS the technological capabilities of a dual-coolant He/PbLi BB for DEMO have been explored. The most promising power cycle in this context is a supercritical CO2 (SCO2) recompression Brayton cycle [Linares et.al., FE&D, 2011]. A RELAP5¿3D model has been prepared to simulate the cycle (a field where little experience exists in the use of the code).

  • Diseño conceptual e ingenieria de detalle de un lazo experimental dual Pb15.7Li/ He (proyecto BCN_LOOP®): una propuesta de proyecto de I+D+i industrial para desarrollos clave en tecnologia nuclear de fusion

     Batet Miracle, Lluis; Reventos Puigjaner, Francesc-josep; Mas de Les Valls Ortiz, Elisabet; Fernández, Iván; Veredas, G.; Abellà, Jordi; Sempere Cebrían, Julià; Sanmartí, Manel; Linares, José Ignacio; Sedano Miguel, Luis Angel
    Reunión Anual de la Sociedad Nuclear Española
    p. 1-11
    Presentation's date: 2012-10-18
    Presentation of work at congresses

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    Análisis de la permeación de tritio en los canales de metal líquido de las envolturas regeneradoras de un reactor de fusión en presencia de burbujas de helio  Open access

     Batet Miracle, Lluis; Mas de Les Valls Ortiz, Elisabet; Sedano Miguel, Luis Angel
    Reunión Anual de la Sociedad Nuclear Española
    Presentation's date: 2012-10-18
    Presentation of work at congresses

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    En el interior de los canales de metal l quido de las envolturas regeneradoras de un reactor de fusi on, la posibilidad de existencia de burbujas de helio nucleado no es remota. El helio se forma junto al tritio en la reacci on de los neutrones escapados del plasma con el litio. La acumulaci on de helio en las super cies de contacto entre la estructura y el ML conllevar a una reducci on de la transferencia de calor, al mismo tiempo que una reducci on en la permeaci on de tritio. La coexistencia de tres fases en contacto: metal l quido, helio y material estructural, convierte al transporte de calor y tritio en fen omenos complejos. Para enriquecer estudios de transporte de tritio realizados en el pasado, se plantea ahora un an alisis de detalle del entorno de una burbuja de helio adherida a la pared de un canal de ML de una envoltura regeneradora. Para el estudio se ha utilizado una herramienta CFD desarrollada sobre el c odigo libre OpenFOAM. El transporte de tritio a trav es de las tres fases y a trav es de cada interfase se ha analizado de forma detallada mediante simulaci on CFD. El modelo incluye los distintos mecanismos de transporte: difusi on en ML y gas; recombinaci on y disociaci on en las interfases. Los resultados obtenidos deben permitir re nar los modelos simpli cados ya utilizados en el c alculo de transporte de tritio en canales de ML en presencia de helio nucleado en las paredes

  • MHD para fusión: parámetros puente entre CFD y códigos de sistema

     Mas de Les Valls Ortiz, Elisabet; Batet Miracle, Lluis; Sedano Miguel, Luis Angel
    Reunión Anual de la Sociedad Nuclear Española
    p. 1-8
    Presentation's date: 2012-10-18
    Presentation of work at congresses

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  • Development of a simulation tool for MHD flows under nuclear fusion conditions  Open access

     Mas de Les Valls Ortiz, Elisabet
    Department of Physics and Nuclear Engineering, Universitat Politècnica de Catalunya
    Theses

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    In Nuclear Fusion Technology, MHD flows can be encountered in liquid metal (LM) breeding blankets, the part of a fusion reactor where tritium, one of the fusion fuels, is to be produced. There are several types of LM breeding blankets, which can be classified according to the fraction of the thermal load extracted by the LM. Such classification provides valuable information on liquid metal flow properties. For instance, if no heat removal is carried out by the LM, its velocity can be quite low, what makes buoyancy the predominant force in front of inertia. The flow inside breeding blanket channels can be very complex, particularly in those blanket types where buoyancy plays a relevant role. The understanding of the flow nature, including the possible instabilities that might appear, the exact knowledge of flow profiles for tritium control purposes, and the prediction of thermal fluxes for thermal efficiency analysis are of great interest for blanket design optimization. In this direction, a thermal-MHD coupled simulation tool has been implemented in the OpenFOAM toolkit. The resultant code can be understood as a preliminary predictive tool for liquid metal breeding blanket channel design. The developed code is a transient 3D tool that accounts for thermal-MHD coupling and can deal with several layers of materials. Various MHD modeling strategies have been studied, starting with the implementation of an induced magnetic field formulation and continuing with an electric potential formulation based on the low magnetic Reynolds approximation, in this case using the conservative formula of the Lorentz force proposed by Ni et al. (2007). Two pressure-velocity couplings have been analyzed. The first one is based on a projection method whereas the second one, which has proved to be more robust, follows a PISO-like algorithm (Weller et al. 1998). The thermal coupling has been achieved by means of the Boussinesq hypothesis. The developed tool accounts for the linear wall function for Hartmann boundary layers from Leboucher (1999), which reduces substantially the CPU time of the simulations. The code also accounts for fluid-solid thermal and electrical coupling by means of implicit coupling of fluid and solid grids. Special attention has been placed in correctly coupling liquid-solid energy transport equations by means of the conservative form of the equations in both domains. All along the development process, validation steps have been carried out with successful results. An alternative thermal-MHD tool has also been implemented following the 2D approach from Sommeria and Moreau (1982). Such code accounts for the 0-equation Q2D turbulence RANS model from Smolentsev and Moreau (2006). Three application cases are considered. In the first case, the integrated effect of volumetric heating and magnetic field on tritium transport in a U-bend flow, as applied to the EU HCLL blanket concept, is studied. The second application case corresponds to the thermal analysis of the blanket design that is being developed in the framework of the Spanish National Project on Breeding Blanket Technologies TECNO_FUS (through CONSOLIDER-INGENIO 2010 Programme). The third and last case includes the instability analysis of a pressure-driven MHD flow in a horizontal channel with a constant thermal load. The application cases have not only shown the code capabilities to simulate liquid metal channels in breeding blankets but, also, have provided a useful know-how on flow properties inside those channels.

    En Tecnologia de Fusió Nuclear, per descriure la circulació de fluids dins dels embolcalls regeneradors de metall líquid (ML) cal recórrer a la magnetohidrodinàmica (MHD). Un embolcall regenerador (o tritigeni) és la zona d'un reactor de fusió on es produeix triti, un dels combustibles de fusió. Els embolcalls regeneradors de ML poden classificar-se atenent a la fracció de la càrrega tèrmica extreta pel ML. Aquesta classificació proporciona informació valuosa sobre les propietats del flux de metall líquid. Per exemple, si el ML no extreu potència tèrmica, la seva velocitat pot ser bastant baixa, el que implica que la força dominant sigui la flotació en front de la inèrcia. El flux dins dels canals d’un embolcall regenerador pot ser molt complex, especialment en aquells tipus d’embolcall on la flotació juga un paper rellevant. La comprensió de la naturalesa del flux, incloent les inestabilitats que podrien aparèixer, el coneixement exacte dels perfils de flux per al control de triti, i la predicció de fluxos tèrmics per a l’anàlisi de l’eficiència tèrmica són de gran interès per a l’optimització del disseny. En aquest sentit, s’ha implementat un codi de simulació acoblada tèrmica-MHD en l’eina de codi lliure OpenFOAM. El codi resultant pot ser entès com una eina predictiva preliminar per al disseny dels canals de ML dels embolcalls regeneradors. El codi desenvolupat permet el càlcul transitori en 3D amb acoblament tèrmic-MHD i pot tractar amb diverses capes de materials. S’ha estudiat diferents models MHD, començant per la implementació d’una formulació basada en el camp magnètic induït i continuant amb una formulació basada en el potencial elèctric mitjançant l’aproximació per a Reynolds magnètics baixos, en aquest darrer cas utilitzant la fórmula conservativa de la força de Lorentz proposada per Ni et al. (2007). S’han analitzat dos acoblaments pressió-velocitat. El primer acoblament es basa en un mètode de projecció, mentre que el segon, que ha demostrat ser més robust, segueix un algorisme tipus PISO (Weller et al. 1998). L’acoblament tèrmic s'ha modelat per mitjà de la hipòtesi de Boussinesq. El codi desenvolupat compta amb la funció de paret lineal de Leboucher (1999) per a les capes límit de Hartmann, cosa que redueix substancialment el temps de CPU de les simulacions. El codi també inclou acoblament tèrmic i magnètic líquid-sòlid mitjançant l'acoblament implícit de les malles del fluid i del sòlid. S’ha tingut una cura especial en realitzar correctament aquest acoblament fluid-sòlid fent ús de la forma conservativa de l’equació d’energia en ambdós dominis. Al llarg del procés de desenvolupament, s’han dut a terme les corresponents validacions amb resultats satisfactoris. També s'ha implementat un codi tèrmic-MHD alternatiu basat en el model MHD 2D de Sommeria i Moreau (1982). Aquest segon codi té implementat el model RANS de 0-equacions de Smolentsev i Moreau (2006) per a la turbulència Q2D. Els codis desenvolupats s’han emprat en tres casos d’interès. En el primer cas, s’ha estudiat l’efecte integrat de l’escalfament volumètric i el camp magnètic en el transport de triti en un canal en U, com el que es pot trobar en el disseny d’embolcall regenerador UE HCLL. En el segon cas, s’ha realitzat una anàlisi tèrmica del disseny d’embolcall que s’està definint dins del Programa Nacional Espanyol en Tecnologia d’Embolcalls Regeneradors TECNO_FUS (a través del Programa CONSOLIDER-INGENIO 2010). En el tercer i últim cas, s’han analitzat les inestabilitats que tenen lloc en fluxos MHD en canals horitzontals amb gradient de pressió extern, amb camp magnètic transversal i amb una càrrega tèrmica uniforme. Els casos d’aplicació no només han demostrat la capacitat del codi per simular canals de metall líquid en embolcalls regeneradors; també han permès caracteritzar el flux a l’interior d’aquests canals.

  • Numerical analysis of MHD-thermofluid flows considering sandwich structures as applied to liquid breeding blankets for fusion technology

     Mas de Les Valls Ortiz, Elisabet; Batet Miracle, Lluis; Medina Iglesias, Vicente Cesar de; Fradera, Jordi; Sedano Miguel, Luis Angel
    PAMIR International Conference on Fundamental and Applied MHD
    p. 73-78
    Presentation's date: 2011-11-05
    Presentation of work at congresses

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  • Influence of thermal performance on design parameters on a He/PbLi Dual Coolant DEMO conceptual blanket design

     Mas de Les Valls Ortiz, Elisabet; Fradera, Jordi; Batet Miracle, Lluis; Sanmarti, Manel; Sedano Miguel, Luis Angel
    International Symposium on Fusion Nuclear Technology
    Presentation's date: 2011-09-11
    Presentation of work at congresses

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  • Estudio paramétrico de un diseñoo conceptual de envoltura regeneradora He/LiPb de doble refrigerante para DEMO

     Mas de Les Valls Ortiz, Elisabet; Batet Miracle, Lluis; Fradera Fernandez, Jorge; Sanmartí, Manel; Sedano Miguel, Luis Angel
    Sociedad Nuclear Española. Reunión
    p. 1-8
    Presentation of work at congresses

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  • Towards the development of thermal-hydraulic models aimed at the auxiliary systems design in nuclear fusion technology

     Batet Miracle, Lluis; Sedano Miguel, Luis Angel; Queraltó, Carlos; Mas de Les Valls Ortiz, Elisabet; Fradera, Jordi; Reventos Puigjaner, Francesc-josep
    RELAP5 International Users Seminar
    Presentation of work at congresses

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  • Numerical analysis of buoyancy effects on liquid metal MHD flows

     Mas de Les Valls Ortiz, Elisabet; Fradera, Jordi; Batet Miracle, Lluis
    Workshop on Numerical Simulations of Magnetohydrodynamic Flows
    Presentation's date: 2010-10
    Presentation of work at congresses

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  • MHD modelling for liquid metal banana-shaped channels for Dual-Coolant breeding blanket design for DEMO

     Mas de Les Valls Ortiz, Elisabet; Fradera, Jordi; Batet Miracle, Lluis; Sedano Miguel, Luis Angel
    Symposium on Fusion Technology
    Presentation's date: 2010-09
    Presentation of work at congresses

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  • Access to the full text
    Flow analysis in the HCLL-TBM ITER channels including MHD and heat transfer  Open access

     Mas de Les Valls Ortiz, Elisabet; Fradera, Jordi; Batet Miracle, Lluis
    European Conference on Computational Fluid Dynamics
    p. 1-9
    Presentation's date: 2010-06
    Presentation of work at congresses

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    One of the key components regarding heat transfer and tritium inventories in deuterium-tritium nuclear fusion reactors is the (tritium) Breeding Blanket, called Test Blanket Module or TBM in ITER experiment. Several designs are going to be tested in ITER, one of those is the HCLL (Helium Cooled Lithium Lead) design. Before being tested, it is of major interest to predict in detail several ow parameters such as pressure drop, tritium inventories and tritium permeation rates through walls. The goal of the present study is to analyze the ow near the gap region (close to the rst wall) in the HCLL-TBM so as to quantify tritium inventories and permeation uxes. To do so, simpli ed C-shaped channels are simulated under ITER speci cations. The ow appears to be very complex and, in order to get the origin of this complexity, the phe- nomenon physics are decoupled. First, the pure hydrodynamic case is simulated; obtaining that the critical Reynolds number is around TBM/ITER speci cations. Second, the MHD ow with perfectly insulating walls is studied and, as expected due to the high Hartmann number, hydrodynamic instabilities disappear. Finally, when heat transfer is introduced, vorticity is generated due to Rayleigh-B enard instabilities at the channel inlet and, as the ow travels through the channel, faster vortices appear in the gap region and in the outlet channel. These vortices originate high tritium concentration zones. Hence, the existence of vortices is of crucial interest for tritium inventories prediction and HCLL design.

  • Recent MHD activities for blanket analysis at UPC

     Mas de Les Valls Ortiz, Elisabet; Fradera, Jordi; Sedano Miguel, Luis Angel; Codina Rovira, Ramon; Badia Rodriguez, Santiago I.; Batet Miracle, Lluis
    Reunión Anual de la Sociedad Nuclear Española
    p. 1-8
    Presentation's date: 2010
    Presentation of work at congresses

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  • CONSOLIDER TECNO-FUS (L.BATET)

     Reventos Puigjaner, Francesc-josep; Mas de Les Valls Ortiz, Elisabet; Fradera Fernandez, Jorge; Batet Miracle, Lluis
    Competitive project

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  • Numeric implementation of two-phase tritium transport models for natural helium nucleated bubbles in lead-lithium. Implications for HCLL breeding blanket channels

     Fradera, Jordi; Batet Miracle, Lluis; Mas de Les Valls Ortiz, Elisabet; Sedano Miguel, Luis Angel
    IEEE/NPSS Symposium on Fusion Engineering
    p. 369-372
    DOI: 10.1109/FUSION.2009.5226440
    Presentation's date: 2009
    Presentation of work at congresses

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  • Desarrollo de herramientas computacionales de simulación acoplada de la MHD y el transporte de tritio en los canales de ITER HCLL

     Mas de Les Valls Ortiz, Elisabet; Batet Miracle, Lluis
    Sociedad Nuclear Española. Reunión
    Presentation of work at congresses

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  • Boundary layer analyses for coupled mixed convection and MHD flow on tritium permeation in ITER HCLL TBM c-shaped channels

     Mas de Les Valls Ortiz, Elisabet; Batet Miracle, Lluis
    25th Symposium on Fusion Technology : 15-19 September 2008
    Presentation of work at congresses

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  • OpenFOAM capabilities for magnetohydrodynamic simulation under nuclear fusion technology conditions

     Mas de Les Valls Ortiz, Elisabet; Batet Miracle, Lluis
    Third OpenFOAM Workshop
    Presentation of work at congresses

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  • Transient solver for low-magnetic Reynolds number simulations

     Mas de Les Valls Ortiz, Elisabet; Batet Miracle, Lluis
    Workshop MHD fundamentals, from liquid-metals to astrophysics
    Presentation of work at congresses

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  • Desarrollo de herramientas computacionales de simulación acoplada de la MHD y el transporte de tritio en los canales de los módulos de ensayo de envoltura ITER HCLL (EU ITER-TBM)

     Mas de Les Valls Ortiz, Elisabet; Batet Miracle, Lluis; Sedano Miguel, Luis Angel
    Reunión Anual de la Sociedad Nuclear Española
    p. 1-8
    Presentation's date: 2008
    Presentation of work at congresses

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  • Resistive MHD simulations with OpenFOAM. Algorithm strategies

     Mas de Les Valls Ortiz, Elisabet; Sedano Miguel, Luis Angel; Batet Miracle, Lluis
    International Workshop on Numerical Simulations of Magnetohydrodynamic Flows
    Presentation of work at congresses

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  • Base de datos del eutéctico Pb15.7Li para TFN

     Mas de Les Valls Ortiz, Elisabet; Batet Miracle, Lluis
    Sociedad Nuclear Española. Reunión
    Presentation of work at congresses

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  • Lead-lithium eutectic material database for nuclear fusion technology

     Mas de Les Valls Ortiz, Elisabet; Batet Miracle, Lluis
    IV International Workshop on Materials for HLM cooled Reactors and Related Technologies
    Presentation of work at congresses

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  • Numerical simulation of the thermal and fluid-dynamic behaviour of fuel-oil in sunk ships

     Perez Segarra, Carlos David; Consul Serracanta, Ricard; Capdevila Paramio, Roser; Oliva Llena, Asensio; Castro Gonzalez, Jesus; Mas de Les Valls Ortiz, Elisabet
    Symposium on Marine Accidental Oil Spills (VERTIMAR-2005)
    p. 37-38
    Presentation of work at congresses

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  • Numerical simulation of the behaviour of thermosyphon systems

     Jaramillo Ibarra, Julian Ernesto; Mas de Les Valls Ortiz, Elisabet; Oliet Casasayas, Carles; Cadafalch Rabasa, Jordi
    International Conference on Solar Heating, Cooling and Buildings
    p. 1-8
    Presentation of work at congresses

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  • VEM2003-20046 Desarrollo de un código específico para la simulación numérica del comportamiento térmico y fluido dinámico de aceites pesados contenidos en el interior de buques hundidos.

     Perez Segarra, Carlos David; Mas de Les Valls Ortiz, Elisabet; Oliva Llena, Asensio; Castro Gonzalez, Jesus; Oliet Casasayas, Carles; Rodriguez Pérez, Ivette Maria; Trias Miquel, Francesc Xavier
    Competitive project

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  • TIC2003-07970 Desarrollo de códigos de altas prestaciones para ordenadores paralelos débilmente enlazados y con fines al diseño optimizado de sistemas y equipos térmicos.

     Oliva Llena, Asensio; Rigola Serrano, Joaquim; Mas de Les Valls Ortiz, Elisabet; Perez Segarra, Carlos David
    Competitive project

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  • Optimization of gas-liquid compact heat exchanges considering their interactions with the rest of the system (COMHEX project).

     Rigola Serrano, Joaquim; Perez Segarra, Carlos David; Mas de Les Valls Ortiz, Elisabet; Torrades Carné, Francesc; Oliet Casasayas, Carles
    Competitive project

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  • Lead-lithium eutectic material database for nuclear fusion technology

     Mas de Les Valls Ortiz, Elisabet; Sedano Miguel, Luis Angel; Batet Miracle, Lluis; Ricapito, I.; Aiello, A.; Gastaldi, O.; Gabriel, F.
    Journal of nuclear materials
    Vol. 376, num. 3, p. 353-357
    Date of publication: 2008-09
    Journal article

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  • Mathematical models for tritium permeation analysis in liquid metal flows with helium bubbles

     Batet Miracle, Lluis; Mas de Les Valls Ortiz, Elisabet; Sedano Miguel, Luis Angel
    Fusion engineering and design
    Vol. 89, num. 7-8, p. 1158-1162
    DOI: 10.1016/j.fusengdes.2014.04.031
    Date of publication: 2014-10-01
    Journal article

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    In LIBRETTO-2 test, evidence was obtained that helium bubbles nucleated and grew in the neutron irradiated PbLi probes. If such phenomenon occurs inside liquid metal (LM) breeding blanket channels, the study of its effect on tritium permeation and heat transfer in the near wall region will acquire utmost importance. The T4F research group has developed in the past a nucleation, growth and transport model for helium bubbles in LM flows, as well as a tritium transport model in such a multi-fluid system. In the present study, we are focused on the near-wall region analysis in order to obtain a wall function that allow reproducing the tritium permeation with coarse meshes and, hence, reduce the computational time. First, we perform some detailed CFD simulations of the near-wall region where bubbles might be attached. In these simulations, tritium diffusion processes as well as tritium recombination and dissociation are modelled. The analysis of such simulations allows us to further understand the complex phenomena and justify the use of simplified models. As a result, a new model for tritium transport across a LM-solid interface partially covered by helium bubbles is developed, implemented and validated. This simplified model can be seen as a wall function for the CFD simulation which substantially reduces computational time. © 2014 Elsevier B.V.

  • Modelling of a supercritical CO2 power cycle for nuclear fusion reactors using RELAP5-3D

     Batet Miracle, Lluis; Álvarez Fernández, Josep Maria; Mas de Les Valls Ortiz, Elisabet; Martínez Quiroga, Víctor Manuel; Perez Ferragut, Marina; Reventos Puigjaner, Francesc-josep; Sedano Miguel, Luis Angel
    Fusion engineering and design
    Vol. 89, num. 4, p. 354-359
    DOI: 10.1016/j.fusengdes.2014.03.018
    Date of publication: 2014-04-01
    Journal article

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    A supercritical recompression CO2 power cycle has been simulated using the system code RELAP5-3D. This code is being developed by INL and has traditionally been used in the simulation of operational and accidental transients in fission nuclear plants. The aim of the work presented here, developed within the framework of the Spanish Fusion Technology Program Consolider TECNO_FUS, is to take advantage of the simulation capabilities of RELAP5-3D in a field where little if any experience exists in the use of the code; i.e., the simulation of the heat fluxes and the thermodynamic cycle that, in a fusion power plant, will convert thermal power from plasma into mechanical power as a previous step to electricity generation. Code capabilities that make it suitable for this purpose are, for instance, the compressor model and the libraries of fluid properties (among them CO2 and LiPb).; The reference plant for the simulation is the one being designed under TECNO_FUS, which is the Spanish proposal for DEMO. The model of the plant includes the primary coolant systems, i.e. helium and LiPb in the Spanish dual coolant modular design (doble refrigerante modular, DRM), compressors, turbine and heat exchangers (Printed Circuit type).; After the model has been set-up, several steady-state calculations have been run to test the performance of the model. After designing some minimal control features and adjusting their parameters, a few transient calculations have been run in order to demonstrate the capabilities of code and model. Finally, strengths and weaknesses of code and model are highlighted, along with some conclusions on their suitability for fusion technology applications.

  • Influence of thermal performance on design parameters of a He/LiPb dual coolant DEMO concept blanket design

     Mas de Les Valls Ortiz, Elisabet; Batet Miracle, Lluis; Medina Iglesias, Vicente Cesar de; Fradera, Jordi; Sanmartí, Manel; Sedano Miguel, Luis Angel
    Fusion engineering and design
    Vol. 87, num. 7-8, p. 969-973
    DOI: 10.1016/j.fusengdes.2012.02.074
    Date of publication: 2012-08
    Journal article

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  • MHD Thermofluid flow simulation of channels with a uniform thermal load as applied to HCLL breeding blankets for fusion technology

     Mas de Les Valls Ortiz, Elisabet; Batet Miracle, Lluis; Medina Iglesias, Vicente Cesar de; Sedano Miguel, Luis Angel
    Magnetohydrodynamics
    Vol. 48, num. 1, p. 157-168
    Date of publication: 2012-01
    Journal article

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  • Qualification of MHD effects in dual-coolant DEMO blanket and approaches to their modelling

     Mas de Les Valls Ortiz, Elisabet; Batet Miracle, Lluis; Medina Iglesias, Vicente Cesar de; Fradera, Jordi; Sedano Miguel, Luis Angel
    Fusion engineering and design
    Vol. 86, num. 9-11, p. 583-589
    DOI: 10.1016/j.fusengdes.2011.03.071
    Date of publication: 2011-10
    Journal article

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  • Numeric implementation of a nucleation, growth and transport model for helium bubbles in lead¿lithium HCLL breeding blanket channels: Theory and code development

     Batet Miracle, Lluis; Fradera, Jordi; Mas de Les Valls Ortiz, Elisabet; Sedano Miguel, Luis Angel
    Fusion engineering and design
    Vol. 86, num. 4-5, p. 421-428
    DOI: 10.1016/j.fusengdes.2011.03.074
    Date of publication: 2011-06
    Journal article

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    Large helium (He) production rates in liquid metal breeding blankets of a DT fusion reactor might have a significant influence in the system design. Low He solubility together with high local concentrations may create the conditions for He cavitation, which would have an impact in the components performance. The paper states that such a possibility is not remote in a helium cooled lithium–lead breeding blanket design. A model based on the Classical Nucleation Theory (CNT) has been developed and implemented in order to have a specific tool able to simulate HCLL systems and identify the key parameters and sensitivities. The nucleation and growth model has been implemented in the open source CFD code OpenFOAM so that transport of dissolved atomic He and nucleated He bubbles can be simulated. At the current level of development it is assumed that void fraction is small enough not to affect either the hydrodynamics or the properties of the liquid metal; thus, bubbles can be represented by means of a passive scalar. He growth and transport has been implemented using the mean radius approach in order to save computational time. Limitations and capabilities of the model are shown by means of zero-dimensional simulation and sensitivity analysis under HCLL breeding unit conditions.

  • Implementation of two-phase tritium models for helium bubbles in HCLL breeding blanket modules

     Fradera, Jordi; Sedano Miguel, Luis Angel; Mas de Les Valls Ortiz, Elisabet; Batet Miracle, Lluis
    Journal of nuclear materials
    Vol. 417, num. 1-3, p. 739-742
    DOI: 10.1016/j.jnucmat.2011.02.008
    Date of publication: 2011
    Journal article

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    Tritium self-sufficiency requirement of future DT fusion reactors involves large helium production rates in the breeding blankets; this might impact on the conceptual design of diverse fusion power reactor units, such as Liquid Metal (LM) blankets. Low solubility, long residence-times and high production rates create the conditions for Helium nucleation, which could mean effective T sinks in LM channels. A model for helium nano-bubble formation and tritium conjugate transport phenomena in liquid Pb17.5Li and EUROFER is proposed. In a first approximation, it has been considered that He bubbles can be represented as a passive scalar. The nucleation model is based on the classical theory and includes a simplified bubble growth model. The model captures the interaction of tritium with bubbles and tritium diffusion through walls. Results show the influence of helium cavitation on tritium inventory and the importance of simulating the system walls instead of imposing fixed boundary conditions.

  • Modelling of integrated effect of volumetric heating and magnetic field on tritium transport in a U-bend flow as applied to HCLL blanket concept

     Mas de Les Valls Ortiz, Elisabet; Batet Miracle, Lluis; Medina Iglesias, Vicente Cesar de; Fradera, Jordi; Sedano Miguel, Luis Angel
    Fusion engineering and design
    Vol. 86, num. 4-5, p. 341-356
    DOI: 10.1016/j.fusengdes.2011.02.075
    Date of publication: 2011
    Journal article

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