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Titolo Data di pubblicazione Autore(i) File
Compact tokamak neutron sources as a first step towards hybrid fission-fusion reactors 1-gen-2013 Bombarda, F.
Engineering validation and engineering design of lithium target facility in Ifmif/Eveda project 1-gen-2014 Micchiche, G.; Nitti, F.
Experimental study of the propellant gas load required for pellet injection with ITER-relevant operating parameters 1-gen-2015 Migliori, S.; Frattolillo, A.
Experiments on the MHD Effect on the Drainage of a LiPb Channel and Supporting Numerical Computations with the Level Set Method 1-gen-2021 Candido, L.; Alberghi, C.; Papa, F.; Ricapito, I.; Utili, M.; Venturini, A.; Zucchetti, M.
Fusion technology activities through the broader approach ifmif-eveda project 1-gen-2013 Micchiche, G. , ENEA,
Lower hybrid current drive for Demo: Physics assessment and technology maturity 1-gen-2013 Tuccillo, A. A.; Ravera, G. L.; Marinucci, M.; Cesario, R.; Castaldo, C.; Cardinali, A.; Barbato, E.; Ceccuzzi, S.
Matter Injection in EU-DEMO: The Preconceptual Design 1-gen-2021 Ploeckl, B.; Lang, P. T.; Frattolillo, A.; Igitkhanov, Y.; P??gouri??, B.; Fable, E.; Day, Chr.; Gliss, C.
Modeling of electromagnetic loads on DEMO first stage divertor 1-gen-2017 Ramogida, G.; Cocilovo, V.
Operational Tritium Inventories in the EU-DEMO Fuel Cycle 1-gen-2022 Schwenzer, J. C.; Day, C.; Giegerich, T.; Santucci, A.
Overview of the Tritium Technologies for the EU DEMO Breeding Blanket 1-gen-2020 Cristescu, I.; Priester, F.; Rapisarda, D.; Santucci, A.; Utili, M.
Permeator Simulations for the EU-DEMO Fuel Cycle 1-gen-2020 Horstensmeyer, Y. N.; Tosti, S.; Santucci, A.; Bruni, G.
Preliminary system modeling for the EUROfusion water cooled lithium lead blanket 1-gen-2017 Del Nevo, A.
Quench propagation in a TF coil of the EU DEMO 1-gen-2017 Turtu, S.; Muzzi, L.; Corato, V.
Radiation Protection Design and Licensing for an Experimental Fusion Facility: The Italian and European Approaches 1-gen-2019 Sandri, S.; Contessa, G. M.; Guardati, M.; Guarracino, M.; Villari, R.
Reliability and availability requirements analysis for DEMO: Fuel Cycle system 1-gen-2015 Borgognoni, F.; Pinna, T.
Reliability estimation for double containment piping 1-gen-2013 Pinna, T.
Review and validation of shutdown dose rate estimation techniques for application to iter 1-gen-2013 Villari, R.
A review of the present status and future prospects of the application of liquid metals for plasma-facing components in magnetic fusion devices 1-gen-2015 Mazzitelli, G.
Sensitivity Analysis and Dimensioning of Reactor-Scale Pd/Ag Permeators for the Tritium Extraction and Removal System of the EU-HCPB Blanket 1-gen-2020 Antunes, R.; Frances, L.; Incelli, M.; Santucci, A.
Sensitivity study for tritium permeation in helium-cooled lead-lithium DEMO blanket with the FUS-TPC code 1-gen-2013 Ciampichetti, A.
Mostrati risultati da 1 a 20 di 21
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