Sfoglia per Rivista  FUSION ENGINEERING AND DESIGN

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Mostrati risultati da 1 a 20 di 411
Titolo Data di pubblicazione Autore(i) File
Activation measurements in support of the 14 MeV neutron calibration of JET neutron monitors 1-gen-2017 Pillon, M.; Loreti, S.
Active toroidal field ripple compensation and MHD feedback control coils in FAST 1-gen-2013 Vlad, G.; Rita, C.; Fusco, V.; Cucchiaro, A.; Crisanti, F.; Crescenzi, F.; Cocilovo, V.; Calabrò, G.; Ramogida, G.
Activity and decay heat calculations for the European DEMO WCLL breeder blanket module including activated LiPb flow 1-gen-2019 Stankunas, G.; Moro, F.; Tidikas, A.
Addressing the feasibility of inboard direct-line injection of high-speed pellets, for core fueling of DEMO 1-gen-2019 Frattolillo, A.; Baylor, L. R.; Bombarda, F.; Cismondi, F.; Colangeli, A.; Combs, S. K.; Day, C.; D'Elia, G.; Gebhart, T. E.; Iannone, F.; Lang, P. T.; Meitner, S. J.; Migliori, S.; Moro, F.; Mozzillo, R.; Pegourie, B.; Ploeckl, B.; Podda, S.; Poggi, F.
Alternative design of DEMO Water Cooled Lithium Lead internal structure 1-gen-2019 Mozzillo, R.; Del Nevo, A.; Martelli, E.; Di Gironimo, G.
Analysis of an ex-vessel break in the ITER divertor cooling loop 1-gen-2006 Porfiri, M. T.
Analysis of nodalization strategies to model a suppression tank for fusion plants with TRACE code 1-gen-2021 Bersano, A.; Mascari, F.; Bertani, C.
Analysis of nodalization strategies to model a suppression tank for fusion plants with TRACE code 1-gen-2021 Bersano, A.; Mascari, F.; Bertani, C.
Analysis of stress induced by plasma disruption on vacuum vessel through multi-physics modeling 1-gen-2020 Cocilovo, V.; Fresa, R.
Analysis of Test D1.1 of the LIFUS5/Mod3 facility for In-box LOCA in WCLL-BB 1-gen-2020 Khani Moghanaki, S.; Galleni, F.; Eboli, M.; Nevo, A. D.; Paci, S.; Forgione, N.
Analysis of the effects of thermal anchors on the reduction of the parasitic load to the EU-DEMO TF coils 1-gen-2021 Viarengo, S.; Allio, A.; Boso, D. P.; Savoldi, L.; Sedlak, K.; Corato, V.
Analysis of the Ingress of Coolant Event tests performed in the upgraded ICE facility aimed at the ECART code validation 1-gen-2020 Paci, S.; Gonfiotti, B.; Martelli, D.; Porfiri, M. T.
Analysis of the thermal-hydraulic behavior of the EU-DEMO WCLL breeding blanket cooling systems during a loss of flow accident 1-gen-2021 Ciurluini, C.; Giannetti, F.; Martelli, E.; Del Nevo, A.; Barucca, L.; Caruso, G.
Analysis of the thermo-mechanical behaviour of the DEMO Water-Cooled Lithium Lead breeding blanket module under normal operation steady state conditions 1-gen-2015 Tincani, A.; Giammusso, R.
Analysis of the thermomechanical behavior of the IFMIF bayonet target assembly under design loading scenarios 1-gen-2015 Serra, M.; Miccichè, G.; Frisoni, M.; Bernardi, D.
Application of ADVANTG to the JET3 – NEXP streaming benchmark experiment 1-gen-2019 Kos, B.; Mosher, S. W.; Kodeli, I. A.; Grove, R. E.; Naish, J.; Obryk, B.; Villari, R.; Batistoni, P.
Application of the mirror procedure to the robustness and fault analysis of Divertor Tokamak Test facility 1-gen-2021 Chiariello, A. G.; Baruzzo, M.; Martone, R.; Pironti, A.; Terranova, D.
Approach in improving reliability of DEMO 1-gen-2020 Pinna, T.; Dongiovanni, D. N.
Architecture of WEST plasma control system 1-gen-2014 Mannori, S.
Assessment of corrosion phenomena in liquid lithium at T < 873 K. A Li(d,n) neutron source as case study 1-gen-2017 Favuzza, P.
Mostrati risultati da 1 a 20 di 411
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