E.T.S. DE INGENIEROS INDUSTRIALES
Ikastegia
IOLE
PALERMO
Ikertzailea 2017-2017 tartean
IOLE PALERMO-rekin lankidetzan egindako argitalpenak (27)
2024
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Challenges towards an acceleration in stellarator reactors engineering: The dual coolant lithium–lead breeding blanket helical-axis advanced stellarator case
Energy, Vol. 289
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Fast generation of parametric neutronic models for stellarators. Coupling HeliasGeom and GEOUNED
Fusion Engineering and Design, Vol. 203
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Overview of European efforts and advances in Stellarator power plant studies
Fusion Engineering and Design, Vol. 202
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Progress in design and experimental activities for the development of an advanced breeding blanket
Nuclear Fusion, Vol. 64, Núm. 5
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Proof-of-principle of parametric stellarator neutronics modeling using Serpent2
Nuclear Fusion, Vol. 64, Núm. 7
2021
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Integration of DEMO hazard piping into the tokamak building
Fusion Engineering and Design, Vol. 168
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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
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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
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Divertor options impact on DEMO nuclear performances
Fusion Engineering and Design, Vol. 130, pp. 32-41
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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
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Large-scale behavior of sandwich-like FCI components within the EU-DCLL operational conditions
Fusion Engineering and Design, Vol. 136, pp. 633-638
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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
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A Monte-Carlo Benchmark of Tripoli-4® and MCNP on ITER neutronics
EPJ Web of Conferences
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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
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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
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Methodological approach for DEMO neutronics in the European PPPT programme: Tools, data and analyses
Fusion Engineering and Design, Vol. 123, pp. 26-31
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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
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Potential irradiation of Cu alloys and tungsten samples in DONES
Nuclear Fusion, Vol. 57, Núm. 12
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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
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Shutdown dose rate assessment with the Advanced D1S method for the European DCLL DEMO
Fusion Engineering and Design, Vol. 122, pp. 163-175