E-LIB Suche - Ergebnisse für: Del Nevo, A

1

W-HYDRA: a new experimental platform for the Water-Cooled L..:

Arena, P. ; Del Nevo, A. ; Eboli, M....
Nuclear Fusion. 64 (2024) 7 - p. 076043 , 2024

Link: https://doi.org/10.1088/..

2

Assessment of the relevancy of ENEA Water Loop facility wit..:

Gonfiotti, B. ; Ciurluini, C. ; Giannetti, F...
Fusion Engineering and Design. 202 (2024) - p. 114375 , 2024

Link: https://doi.org/10.1016/..

3

Thermal-hydraulic assessment of the Steam Generator mock-up..:

Caterino, D. ; Del Nevo, A. ; Eboli, M....
Fusion Engineering and Design. 201 (2024) - p. 114237 , 2024

Link: https://doi.org/10.1016/..

4

Study of the thermo-mechanical performances of the EU-DEMO ..:

Giambrone, S. ; Arena, P. ; Bongiovì, G....
Fusion Engineering and Design. 192 (2023) - p. 113837 , 2023

Link: https://doi.org/10.1016/..

5

State-of-the-art review of the T/H system codes RELAP5 for ..:

Lorusso, P. ; Polidori, M. ; Del Nevo, A....
Nuclear Engineering and Design. 414 (2023) - p. 112627 , 2023

Link: https://doi.org/10.1016/..

6

The LIFUS5 separate effect test facility experimental progr..:

Eboli, M. ; Ciampichetti, A. ; Giannetti, F...
Nuclear Engineering and Design. 411 (2023) - p. 112425 , 2023

Link: https://doi.org/10.1016/..

7

Transient analysis of a locked rotor/shaft seizure accident..:

Ciurluini, C. ; D'Onorio, M. ; Giannetti, F...
Fusion Engineering and Design. 187 (2023) - p. 113396 , 2023

Link: https://doi.org/10.1016/..

8

Assessment of INSPYRE-extended fuel performance codes again..:

Luzzi, L. ; Barani, T. ; Boer, B....
Nuclear Engineering and Technology. 55 (2023) 3 - p. 884-894 , 2023

Link: https://doi.org/10.1016/..

9

Maturation of critical technologies for the DEMO balance of..:

Barucca, L. ; Hering, W. ; Perez Martin, S....
Fusion Engineering and Design. 179 (2022) - p. 113096 , 2022

Link: https://doi.org/10.1016/..

10

Tokamak cooling systems and power conversion system options:

Moscato, I. ; Barucca, L. ; Bubelis, E....
Fusion Engineering and Design. 178 (2022) - p. 113093 , 2022

Link: https://doi.org/10.1016/..

11

Corrigendum to "MHD forced convection flow in dielectric an..:

Siriano, S. ; Tassone, A. ; Caruso, G..
Fusion Engineering and Design. 171 (2021) - p. 112284 , 2021

Link: https://doi.org/10.1016/..

12

The TRANSURANUS fuel performance code:

, In: Nuclear Power Plant Design and Analysis Codes,

Magni, A. ; Del Nevo, A. ; Luzzi, L.... - p. 161-205 , 2021

Link: https://doi.org/10.1016/..

13

Pre-conceptual design of EU DEMO balance of plant systems: ..:

Barucca, L. ; Bubelis, E. ; Ciattaglia, S....
Fusion Engineering and Design. 169 (2021) - p. 112504 , 2021

Link: https://doi.org/10.1016/..

14

Total loss of flow benchmark in CIRCE-HERO integral test fa..:

Lorusso, P. ; Del Nevo, A. ; Narcisi, V....
Nuclear Engineering and Design. 376 (2021) - p. 111086 , 2021

Link: https://doi.org/10.1016/..

15

List of contributors:

, In: Nuclear Power Plant Design and Analysis Codes,

Adorni, M. ; Bals, Christine ; Beck, Sara... - p. ix-xi , 2021

Link: https://doi.org/10.1016/..