Simone Siriano

Mr. Simone Siriano

Sapienza University of Rome, Rome, Lazio, Italy
orcid

Research Focus & Metrics

Academic Career Length

7Years (2020-Present)

(Calculated once Scilit publication data is synced: current year − year of first publication + 1)

Representative Publications

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7 December 2021 in Applied Sciences
Verified
Journal Article
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PAPietro ARENA
Pietro ARENA
Alessandro Del NevoAlessandro Del Nevo
Alessandro Del Nevo
Fabio MoroFabio Moro
Fabio Moro
SNSimone Noce
Simone Noce
Rocco MozzilloRocco Mozzillo
Rocco Mozzillo
GBGaetano Bongiovi
Gaetano Bongiovi
The Water-Cooled Lead–Lithium Breeding Blanket (WCLL BB) is one of the two blanket concept candidates to become the driver blanket of the EU-DEMO reactor. The design was enacted with a holistic approach. The influence that neutronics, thermal-hydraulics (TH), thermo-mechanics (TM) and magneto-hydro-dynamics (MHD) may have on the design were considered at the same time. This new approach allowed for the design team to create a WCLL BB layout that is able to comply with different foreseen requirements in terms of integration, tritium self-sufficiency, and TH and TM needs. In this paper, the rationale behind the design choices and the main characteristics of the WCLL BB needed for the EU-DEMO are reported and discussed. Finally, the main achievements reached during the pre-conceptual design phase and some remaining open issues to be further investigated in the upcoming conceptual design phase are reported as well.

20 February 2023 in Energies
Verified
Journal Article
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PAPietro ARENA
Pietro ARENA
GBGaetano Bongiovi
Gaetano Bongiovi
ICIlenia Catanzaro
Ilenia Catanzaro
CCCristiano Ciurluini
Cristiano Ciurluini
ACAldo Collaku
Aldo Collaku
marco utilimarco utili
marco utili
The water-cooled lead lithium breeding blanket (WCLL BB) is one of two BB candidate concepts to be chosen as the driver blanket of the EU-DEMO fusion reactor. Research activities carried out in the past decade, under the umbrella of the EUROfusion consortium, have allowed a quite advanced reactor architecture to be achieved. Moreover, significant efforts have been made in order to develop the WCLL BB pre-conceptual design following a holistic approach, identifying interfaces between components and systems while respecting a system engineering approach. This paper reports a description of the current WCLL BB architecture, focusing on the latest modifications in the BB reference layout aimed at evolving the design from its pre-conceptual version into a robust conceptual layout. In particular, the main rationale behind design choices and the BB’s overall performances are highlighted. The present paper also gives an overview of the integration between the BB and the different in-vessel systems interacting with it. In particular, interfaces with the tritium extraction and removal (TER) system and the primary heat transfer system (PHTS) are described. Attention is also paid to auxiliary systems devoted to heat the plasma, such as electron cyclotron heating (ECH). Indeed, the integration of this system in the BB will strongly impact the segment design since it envisages the introduction of significant cut-outs in the BB layout. A preliminary CAD model of the central outboard blanket (COB) segment housing the ECH cut-out has been set up and is reported in this paper. The chosen modeling strategy, adopted loads and boundary conditions, as well as obtained results, are reported in the paper and critically discussed.

1 November 2020 in Fusion Engineering and Design
Verified
Journal Article
Closed access
ATAlessandro Tassone
Alessandro Tassone
SSSimone Siriano
Simone Siriano
GCGianfranco Caruso
Gianfranco Caruso
MUMarco Utili
Marco Utili
ANAlessandro Del Nevo
Alessandro Del Nevo

25 April 2022 in Fluids
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Journal Article
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SSSimone Siriano
Simone Siriano
NANéstor Vinicio Balcázar Arciniega
Néstor Vinicio Balcázar Arciniega
ATAlessandro Tassone
Alessandro Tassone
JRJoaquim Rigola
Joaquim Rigola
GCGianfranco Caruso
Gianfranco Caruso
The breeding blanket is one of the fundamental components of a nuclear fusion reactor and is responsible for the fuel production, generating tritium through neutronic capture reaction between lithium and neutrons. Lithium is a liquid PbLi alloy and the helium formed as reaction by-product can coalesce into bubbles, generating a two-phase mixture with a high-density ratio (ηρ∼O5). These bubbles can accumulate and stagnate within the blanket channels with potentially harmful consequences. In this work, the interIsoFoam solver of OpenFOAM v2012 is used to simulate bubble motion for a two-phase mixture representative of the He-PbLi system to test its potential for future developments in the field of fusion. In a first phase, several traditional benchmarks were carried out, both 2D and 3D, and considering the two variants of the VOF method implemented in the solver, isoAdvector and plicRDF. Subsequently, He bubbles of different diameters rising in liquid PbLi (ηρ=1.2×105) were analysed to investigate different regimes. For a Eötvös number (Eo) greater than 10, it was possible to recreate the axisymmetric, skirted, oscillatory regimes and the peripheral and central breakup regimes. For Eo < 10, non-physical deformations of the interface are observed, probably generated by spurious velocities that have a greater impact on the solution for very small bubbles and rising velocities.

9 February 2024 in Fusion Engineering and Design
Verified
Journal Article
Open access
SSSimone Siriano
Simone Siriano
LMLorenzo Melchiorri
Lorenzo Melchiorri
SPSonia Pignatiello
Sonia Pignatiello
ATAlessandro Tassone
Alessandro Tassone

1 November 2020 in Fusion Engineering and Design
Verified
Journal Article
Closed access
SSSimone Siriano
Simone Siriano
ATAlessandro Tassone
Alessandro Tassone
GCGianfranco Caruso
Gianfranco Caruso
Alessandro Del NevoAlessandro Del Nevo
Alessandro Del Nevo