Challenges towards an acceleration in stellarator reactors engineering: The dual coolant lithium–lead breeding blanket helical-axis advanced stellarator case

Iole Palermo (Corresponding author), Javier Alguacil, Juan Pablo Catalán, Iván Fernández-Berceruelo, Jorrit Lion, Jose Ángel Noguerón Valiente, David Sosa, David Rapisarda, Fernando R. Urgorri, Felix Warmer, Richard Kembleton

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Samenvatting

Under the ambitious EUROfusion mission of “bringing the stellarator line to technological maturity”, the development of a Dual Coolant Lithium–Lead (DCLL) Breeding Blanket (BB) for a Helical-Axis Advanced Stellarator (HELIAS) started. The BB is the crucial systems to achieve tritium self-sufficiency in fusion power plants. The DCLL has potentialities to answer the challenges posed by complex HELIAS configuration, having liquid breeder and decoupled first wall (FW) and breeding zone circuits. Both characteristics are being empowered to simplify remote maintenance and integration of the BB segments. Hence, a “quasi-toroidal” BB segmentation has been proposed to minimize the magnetohydrodynamic pressure drop eschewing complex electrical insulating components while hindering maintenance. Such controversy motivated the use of a detached FW small panels manageable through ports. On this basis, a decoupled Capillary Porous System FW has been assessed under thermal-hydraulics and neutronics point of view. Moreover, ad-hoc tools have been developed for the parametrization of models and convergence toward a viable DCLL HELIAS design, speeding-up the coupling of computer-aided design modelling and analyses. Such novel strategies are described in view of a potential acceleration of the stellarator reactor engineering and by providing an overview of the stellarator challenges inside a global context.

Originele taal-2Engels
Artikelnummer129970
Aantal pagina's17
TijdschriftEnergy
Volume289
DOI's
StatusGepubliceerd - 15 feb. 2024

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Publisher Copyright:
© 2023 The Authors

Financiering

This work has been carried out within the framework of the EUROfusion Consortium, funded by the European Union via the Euratom Research and Training Programme (Grant Agreement No 101052200 — EUROfusion). Views and opinions expressed are however those of the author(s) only and do not necessarily reflect those of the European Union or the European Commission. Neither the European Union nor the European Commission can be held responsible for them. This work has been also partially supported by Comunidad de Madrid under TECHNOFUSION(III)-CM , S2018/EMT-4437 .

FinanciersFinanciernummer
Comunidad de MadridS2018/EMT-4437
European Commission101052200 — EUROfusion

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