Modeling the Transport of Activated Corrosion Products in the WCLL PbLi Loop for ITER and the EU DEMO With the GETTHEM Code

This work presents the results of the implementation in the GEneral Tokamak THErmal-hydraulic Model of available models for the generation and transport of any dispersed material in flowing PbLi eutectic mixture. In particular, the focus is on Activated Corrosion Products circulating as solid suspen...

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Main Authors: Fabrizio Lisanti, Pietro Arena, Roberto Bonifetto, Antonio Froio, Francisco Alberto Hernandez Gonzalez, Gandolfo Alessandro Spagnuolo, Roberto Zanino
Format: Article
Language:English
Published: IEEE 2023-01-01
Series:IEEE Access
Subjects:
Online Access:https://ieeexplore.ieee.org/document/10058966/
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author Fabrizio Lisanti
Pietro Arena
Roberto Bonifetto
Antonio Froio
Francisco Alberto Hernandez Gonzalez
Gandolfo Alessandro Spagnuolo
Roberto Zanino
author_facet Fabrizio Lisanti
Pietro Arena
Roberto Bonifetto
Antonio Froio
Francisco Alberto Hernandez Gonzalez
Gandolfo Alessandro Spagnuolo
Roberto Zanino
author_sort Fabrizio Lisanti
collection DOAJ
description This work presents the results of the implementation in the GEneral Tokamak THErmal-hydraulic Model of available models for the generation and transport of any dispersed material in flowing PbLi eutectic mixture. In particular, the focus is on Activated Corrosion Products circulating as solid suspension in the PbLi loop of the Water-Cooled Lithium-Lead Breeding Blanket of the EU DEMO fusion reactor. A simple test case is used to show that the distribution of the concentration of activated corrosion products at any point of the PbLi loop, both in the water-cooled lithium-lead breeding blanket and in the related ITER Test Blanket System, can be determined by the model. Moreover, thanks to the model’s dynamic nature, operational transients can be simulated; for instance, starting from zero impurities in the PbLi alloy, the evolution of the concentration of corrosion products is shown, until the steady-state is reached. The results obtained with this tool can be useful not only for radiological safety purposes, but also because activated corrosion products may affect the PbLi flow itself and the efficiency of the tritium removal system, with consequences on the achievable Tritium Breeding Ratio. A rigorous verification of the model is also performed.
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spelling doaj.art-7db47bb961414dd5b1f458bbc4d7e9362023-03-10T00:00:24ZengIEEEIEEE Access2169-35362023-01-0111226142262810.1109/ACCESS.2023.325290510058966Modeling the Transport of Activated Corrosion Products in the WCLL PbLi Loop for ITER and the EU DEMO With the GETTHEM CodeFabrizio Lisanti0Pietro Arena1https://orcid.org/0000-0002-2860-4717Roberto Bonifetto2https://orcid.org/0000-0002-3557-9177Antonio Froio3https://orcid.org/0000-0003-2526-2309Francisco Alberto Hernandez Gonzalez4https://orcid.org/0000-0003-2538-9377Gandolfo Alessandro Spagnuolo5https://orcid.org/0000-0001-8416-3349Roberto Zanino6https://orcid.org/0000-0003-0334-8275NEMO Group, Dipartimento Energia “Galileo Ferraris,” Politecnico di Torino, Turin, ItalyENEA C. R. Brasimone, Camugnano (BO), ItalyNEMO Group, Dipartimento Energia “Galileo Ferraris,” Politecnico di Torino, Turin, ItalyNEMO Group, Dipartimento Energia “Galileo Ferraris,” Politecnico di Torino, Turin, ItalyInstitut für Neutronenphysik und Reaktortechnik, Karlsruher Institut für Technologie, Karlsruhe, GermanyFusion Technology Department, EUROfusion Consortium, Garching bei München, GermanyNEMO Group, Dipartimento Energia “Galileo Ferraris,” Politecnico di Torino, Turin, ItalyThis work presents the results of the implementation in the GEneral Tokamak THErmal-hydraulic Model of available models for the generation and transport of any dispersed material in flowing PbLi eutectic mixture. In particular, the focus is on Activated Corrosion Products circulating as solid suspension in the PbLi loop of the Water-Cooled Lithium-Lead Breeding Blanket of the EU DEMO fusion reactor. A simple test case is used to show that the distribution of the concentration of activated corrosion products at any point of the PbLi loop, both in the water-cooled lithium-lead breeding blanket and in the related ITER Test Blanket System, can be determined by the model. Moreover, thanks to the model’s dynamic nature, operational transients can be simulated; for instance, starting from zero impurities in the PbLi alloy, the evolution of the concentration of corrosion products is shown, until the steady-state is reached. The results obtained with this tool can be useful not only for radiological safety purposes, but also because activated corrosion products may affect the PbLi flow itself and the efficiency of the tritium removal system, with consequences on the achievable Tritium Breeding Ratio. A rigorous verification of the model is also performed.https://ieeexplore.ieee.org/document/10058966/Activated corrosion productsblanketITERmodellingnuclear fusion
spellingShingle Fabrizio Lisanti
Pietro Arena
Roberto Bonifetto
Antonio Froio
Francisco Alberto Hernandez Gonzalez
Gandolfo Alessandro Spagnuolo
Roberto Zanino
Modeling the Transport of Activated Corrosion Products in the WCLL PbLi Loop for ITER and the EU DEMO With the GETTHEM Code
IEEE Access
Activated corrosion products
blanket
ITER
modelling
nuclear fusion
title Modeling the Transport of Activated Corrosion Products in the WCLL PbLi Loop for ITER and the EU DEMO With the GETTHEM Code
title_full Modeling the Transport of Activated Corrosion Products in the WCLL PbLi Loop for ITER and the EU DEMO With the GETTHEM Code
title_fullStr Modeling the Transport of Activated Corrosion Products in the WCLL PbLi Loop for ITER and the EU DEMO With the GETTHEM Code
title_full_unstemmed Modeling the Transport of Activated Corrosion Products in the WCLL PbLi Loop for ITER and the EU DEMO With the GETTHEM Code
title_short Modeling the Transport of Activated Corrosion Products in the WCLL PbLi Loop for ITER and the EU DEMO With the GETTHEM Code
title_sort modeling the transport of activated corrosion products in the wcll pbli loop for iter and the eu demo with the getthem code
topic Activated corrosion products
blanket
ITER
modelling
nuclear fusion
url https://ieeexplore.ieee.org/document/10058966/
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