Publikationen (27) Publikationen von IOLE PALERMO

2024

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

    Energy, Vol. 289

  2. Fast generation of parametric neutronic models for stellarators. Coupling HeliasGeom and GEOUNED

    Fusion Engineering and Design, Vol. 203

  3. Overview of European efforts and advances in Stellarator power plant studies

    Fusion Engineering and Design, Vol. 202

  4. Progress in design and experimental activities for the development of an advanced breeding blanket

    Nuclear Fusion, Vol. 64, Núm. 5

  5. Proof-of-principle of parametric stellarator neutronics modeling using Serpent2

    Nuclear Fusion, Vol. 64, Núm. 7

2021

  1. Integration of DEMO hazard piping into the tokamak building

    Fusion Engineering and Design, Vol. 168

  2. Radiation level in the DEMO tokamak complex due to activated flowing water: Impact on the architecture of the building

    Fusion Engineering and Design, Vol. 166

2020

  1. Impact of the flowing activated water on maintenance and electronic functioning for the pre-conceptual design of the European DEMO fusion reactor

    Fusion Engineering and Design, Vol. 153

2018

  1. Divertor options impact on DEMO nuclear performances

    Fusion Engineering and Design, Vol. 130, pp. 32-41

  2. Integration of the Neutral Beam Injector System into the DCLL Breeding Blanket for the EU DEMO

    IEEE Transactions on Plasma Science, Vol. 46, Núm. 7, pp. 2708-2716

  3. Large-scale behavior of sandwich-like FCI components within the EU-DCLL operational conditions

    Fusion Engineering and Design, Vol. 136, pp. 633-638

  4. Magnetohydrodynamic and thermal analysis of PbLi flows in poloidal channels with flow channel insert for the EU-DCLL blanket

    Nuclear Fusion, Vol. 58, Núm. 10

2017

  1. A Monte-Carlo Benchmark of Tripoli-4® and MCNP on ITER neutronics

    EPJ Web of Conferences

  2. Design and fabrication of a Permeator Against Vacuum prototype for small scale testing at Lead-Lithium facility

    Fusion Engineering and Design, Vol. 124, pp. 871-875

  3. Design of a permeator against vacuum for tritium extraction from eutectic lithium-lead in a DCLL DEMO

    Fusion Engineering and Design, Vol. 117, pp. 226-231

  4. Methodological approach for DEMO neutronics in the European PPPT programme: Tools, data and analyses

    Fusion Engineering and Design, Vol. 123, pp. 26-31

  5. Optimization process for the design of the DCLL blanket for the European DEMOnstration fusion reactor according to its nuclear performances

    Nuclear Fusion, Vol. 57, Núm. 7

  6. Potential irradiation of Cu alloys and tungsten samples in DONES

    Nuclear Fusion, Vol. 57, Núm. 12

  7. Radiological impact mitigation of waste coming from the European fusion reactor DEMO with DCLL breeding blanket

    Fusion Engineering and Design, Vol. 124, pp. 1257-1262

  8. Shutdown dose rate assessment with the Advanced D1S method for the European DCLL DEMO

    Fusion Engineering and Design, Vol. 122, pp. 163-175