Iole Palermo

Overview of the European breeding blanket programme for HELIAS 5-B: dual coolant lead–lithium design, integration and tools

Iole Palermo, Javier Alguacil, G. Bongiovì, Juan Pablo Catalán et autres

Abstract As part of EUROfusion’s mission to bring stellarators to technological maturity, the stellarator power plant studies (SPPS) work package prospective R&D (WPPRD) began in 2021 to develop a HELIAS-class power plant. Building on DEMO tokamak experience, European teams are designing a …

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Progress on the design and integration of a decoupled Capillary Porous System based First Wall for HELIAS

Jose A. Nogueron, Iván Fernández, David Rapisarda, Fernando R. Urgorri et autres

Within EUROfusion activities towards a conceptual design for a Helical Axis Advanced Stellarator (HELIAS) demonstration reactor, CIEMAT is developing a decoupled First Wall (FW) concept. The proposed approach makes use of a liquid metal (LM) as the plasma-facing material (PFM) and decouples …

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Assessment of EUROFER97, tungsten and CuCrZr alloy transmutation effects under IFMIF-DONES and DEMO conditions

Irene Álvarez, M. Anguiano, Fernando Mota, Rebeca Hernández et autres

Water-cooled lead and ceramic breeder (WLCB) breeding blanket (BB) for the EU DEMO: Neutronic campaigns for T breeding optimization

Iole Palermo, Francisco Alberto Hernández, Salvatore D’Amico, Jin Hun Park et autres

• Water-cooled Lead and Ceramic Breeder Advanced BB explored for DEMO. • Neutronic simulation campaigns conducted to optimize performance. • Key design parameters varied to achieve the best Tritium Breeding Ratio. • Varied layouts, cooling, 6 Li, packing factors, multiplier and breeder …

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Assessment of EUROFER97, tungsten and CuCrZr alloy transmutation effects under IFMIF-DONES and DEMO conditions

I. Álvarez, M. Anguiano, F. Mota, Rebeca Hernández et autres

IFMIF-DONES (International Fusion Materials Irradiation Facility – DEMO-Oriented Neutron Source) is a specialised neutron irradiation facility designed to generate critical materials data needed for the construction of the DEMO (DEMOnstration) fusion power plant. This study aims to analyse and characterise the transmutation …

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Advanced materials to enhance the nuclear performances of the high temperature Dual Coolant Lithium lead breeding blanket for the EU DEMO

David Sosa, Iole Palermo, Iván Fernández, Javier Alguacil et autres

The evolution of the Dual Coolant Lithium Lead (DCLL) Breeding Blanket (BB) in the EUROfusion framework has led to the implementation of a Single Module Segment (SMS) architecture whose particularity is that it introduces the use of ceramic channels through which the …

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Initial evaluation of miniature ultra-high-field commercial stellarator reactors with breeding external to resistive coils

Vicente Queral, E. Rincón, A. de Castro, Iván Fernández et autres

The working parameters and challenges of ultra-high-field pulsed commercial stellarator reactors of small plasma volume with breeding external to resistive coils ($transposed$ stellarator) are studied. They may allow production of commercial heat and electricity in a tiny and simple device, and contribute …

Assessment of the possibility of irradiating tungsten and Cu-alloys in IFMIF-DONES using a realistic specimens configuration

I. Álvarez, M. Anguiano, F. Mota, Rebeca Hernández et autres

Abstract IFMIF-DONES (International Fusion Materials Irradiation Facility-DEMO Oriented NEutron Source) is a facility whose purpose is to obtain data on materials by irradiating them under conditions equivalent to those of the DEMO (DEMOstration) fusion reactor. Tungsten and CuCrZr alloy are two candidate …

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Assessment of Eurofer97, Tungsten and Cucrzr Alloy Transmutation Effects Under Ifmif-Dones and Demo Conditions

Irene Álvarez-Castro, M. Anguiano, F. Mota, Rebeca Hernández et autres

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Superior performance of amorphous alumina coatings over polycrystalline alumina for fusion reactor applications

Marcelo Roldán, Marta Malo, Fernando Jose Sanchez, Iole Palermo et autres

Comparative analysis of neutronic features for various specimen payload configurations within the IFMIF-DONES HFTM

I. Álvarez, M. Anguiano, F. Mota, Rebeca Hernández et autres

• IFMIF-DONES is a neutron irradiation facility specifically designed to obtain data on material irradiation for the construction of DEMO fusion power plant. • This study aims to investigate and compare the effect of utilizing different realistic models of specimen distributions during …

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"Exploring the role of lithium in Al2O3 tritium permeation barrier development: A crucial challenge for fusion reactor progress"

E. Carella, Guillermo de la Cuerda-Velazquez, Massimo Angiolini, R. González-Arrabal et autres

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