Hybrid 1D + 2D Modelling for the Assessment of the Heat Transfer in the EU DEMO Water-Cooled Lithium-Lead Manifolds

The European demonstration fusion power reactor (EU DEMO) tokamak will be the first European fusion device to produce electricity and to include a breeding blanket (BB). In the framework of the design of the EU DEMO BB, the analysis of the heat transfer between the inlet and outlet manifold of the c...

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Main Authors: Antonio Froio, Andrea Bertinetti, Alessandro Del Nevo, Laura Savoldi
Format: Article
Language:English
Published: MDPI AG 2020-07-01
Series:Energies
Subjects:
Online Access:https://www.mdpi.com/1996-1073/13/14/3525
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author Antonio Froio
Andrea Bertinetti
Alessandro Del Nevo
Laura Savoldi
author_facet Antonio Froio
Andrea Bertinetti
Alessandro Del Nevo
Laura Savoldi
author_sort Antonio Froio
collection DOAJ
description The European demonstration fusion power reactor (EU DEMO) tokamak will be the first European fusion device to produce electricity and to include a breeding blanket (BB). In the framework of the design of the EU DEMO BB, the analysis of the heat transfer between the inlet and outlet manifold of the coolant is needed, to assess the actual cooling capability of the water entering the cooling channels, as well as the actual coolant outlet temperature from the machine. The complex, fully three-dimensional conjugate heat transfer problem is reduced here with a novel approach to a simpler one, decoupling the longitudinal and transverse scales for the heat transport by developing correlations for a conductive heat-transfer problem. While in the longitudinal direction a standard 1D model for the heat transport by fluid advection is adopted, a set of 2D finite elements analyses are run in the transverse direction, in order to lump the 2D heat conduction effects in suitable correlations. Such correlations are implemented in a 1D finite volume model with the 1D GEneral Tokamak THErmal-hydraulic Model (GETTHEM) code (Politecnico di Torino, Torino, Italy); the proposed approach thus reduces the 3D problem to a 1D one, allowing a parametric evaluation of the heat transfer in the entire blanket with a reduced computational cost. The deviation from nominal inlet and outlet temperature values, for the case of the Water-Cooled Lithium-Lead BB concept, is found to be always below 1.4 K and, in some cases, even to be beneficial. Consequently, the heat transfer among the manifolds at different temperatures can be safely (and conservatively) neglected.
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spelling doaj.art-f28fbee65b44401f9629f5862a22d7e52023-11-20T06:12:09ZengMDPI AGEnergies1996-10732020-07-011314352510.3390/en13143525Hybrid 1D + 2D Modelling for the Assessment of the Heat Transfer in the EU DEMO Water-Cooled Lithium-Lead ManifoldsAntonio Froio0Andrea Bertinetti1Alessandro Del Nevo2Laura Savoldi3NEMO Group, Dipartimento Energia “Galileo Ferraris”, Politecnico di Torino, 10129 Torino, ItalyNEMO Group, Dipartimento Energia “Galileo Ferraris”, Politecnico di Torino, 10129 Torino, ItalyENEA FSN-ING-SIS, CR Brasimone, 40032 Camugnano (BO), ItalyMAHTEP Group, Dipartimento Energia “Galileo Ferraris”, Politecnico di Torino, 10129 Torino, ItalyThe European demonstration fusion power reactor (EU DEMO) tokamak will be the first European fusion device to produce electricity and to include a breeding blanket (BB). In the framework of the design of the EU DEMO BB, the analysis of the heat transfer between the inlet and outlet manifold of the coolant is needed, to assess the actual cooling capability of the water entering the cooling channels, as well as the actual coolant outlet temperature from the machine. The complex, fully three-dimensional conjugate heat transfer problem is reduced here with a novel approach to a simpler one, decoupling the longitudinal and transverse scales for the heat transport by developing correlations for a conductive heat-transfer problem. While in the longitudinal direction a standard 1D model for the heat transport by fluid advection is adopted, a set of 2D finite elements analyses are run in the transverse direction, in order to lump the 2D heat conduction effects in suitable correlations. Such correlations are implemented in a 1D finite volume model with the 1D GEneral Tokamak THErmal-hydraulic Model (GETTHEM) code (Politecnico di Torino, Torino, Italy); the proposed approach thus reduces the 3D problem to a 1D one, allowing a parametric evaluation of the heat transfer in the entire blanket with a reduced computational cost. The deviation from nominal inlet and outlet temperature values, for the case of the Water-Cooled Lithium-Lead BB concept, is found to be always below 1.4 K and, in some cases, even to be beneficial. Consequently, the heat transfer among the manifolds at different temperatures can be safely (and conservatively) neglected.https://www.mdpi.com/1996-1073/13/14/3525nuclear fusionEU DEMObreeding blanketwater-cooled lithium-lead (WCLL)thermal-hydraulicssystem-level modelling
spellingShingle Antonio Froio
Andrea Bertinetti
Alessandro Del Nevo
Laura Savoldi
Hybrid 1D + 2D Modelling for the Assessment of the Heat Transfer in the EU DEMO Water-Cooled Lithium-Lead Manifolds
Energies
nuclear fusion
EU DEMO
breeding blanket
water-cooled lithium-lead (WCLL)
thermal-hydraulics
system-level modelling
title Hybrid 1D + 2D Modelling for the Assessment of the Heat Transfer in the EU DEMO Water-Cooled Lithium-Lead Manifolds
title_full Hybrid 1D + 2D Modelling for the Assessment of the Heat Transfer in the EU DEMO Water-Cooled Lithium-Lead Manifolds
title_fullStr Hybrid 1D + 2D Modelling for the Assessment of the Heat Transfer in the EU DEMO Water-Cooled Lithium-Lead Manifolds
title_full_unstemmed Hybrid 1D + 2D Modelling for the Assessment of the Heat Transfer in the EU DEMO Water-Cooled Lithium-Lead Manifolds
title_short Hybrid 1D + 2D Modelling for the Assessment of the Heat Transfer in the EU DEMO Water-Cooled Lithium-Lead Manifolds
title_sort hybrid 1d 2d modelling for the assessment of the heat transfer in the eu demo water cooled lithium lead manifolds
topic nuclear fusion
EU DEMO
breeding blanket
water-cooled lithium-lead (WCLL)
thermal-hydraulics
system-level modelling
url https://www.mdpi.com/1996-1073/13/14/3525
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