I agree that this site is using cookies. You can find further informations here.
X
Bubelis, E.
72  results:
Search for persons X
?
1

Corrigendum to "Numerical studies of power oscillations ind..:

Chen, X.-N. ; Rineiski, A. ; Perez-Martin, S...
Annals of Nuclear Energy.  186 (2023)  - p. 109791 , 2023
Link: https://doi.org/10.1016/..
 
?
2

Numerical studies of power oscillations induced by sodium b..:

Chen, X.-N. ; Rineiski, A. ; Perez-Martin, S...
Annals of Nuclear Energy.  183 (2023)  - p. 109642 , 2023
Link: https://doi.org/10.1016/..
 
?
3

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/..
 
?
4

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/..
 
?
5

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/..
 
?
6

Preliminary CAD implementation of EU-DEMO primary heat tran..:

Tarallo, A. ; Moscato, I. ; Bubelis, E..
Fusion Engineering and Design.  146 (2019)  - p. 2062-2065 , 2019
Link: https://doi.org/10.1016/..
 
?
7

Progress in EU Breeding Blanket design and integration:

Cismondi, F. ; Boccaccini, L.V. ; Aiello, G....
Fusion Engineering and Design.  136 (2018)  - p. 782-792 , 2018
Link: https://doi.org/10.1016/..
 
?
8

Stress-testing the ALFRED design – Part I: Impact of nuclea..:

Grasso, G. ; Lodi, F. ; Romojaro, P....
Progress in Nuclear Energy.  106 (2018)  - p. 372-386 , 2018
Link: https://doi.org/10.1016/..
 
?
9

System codes benchmarking on a low sodium void effect SFR h..:

Bubelis, E. ; Tosello, A. ; Pfrang, W....
Nuclear Engineering and Design.  320 (2017)  - p. 325-345 , 2017
Link: https://doi.org/10.1016/..
 
?
10

Safety studies for the MYRRHA critical core with the SIMMER..:

Chen, X-N. ; Li, R. ; Belloni, F....
Annals of Nuclear Energy.  110 (2017)  - p. 1030-1042 , 2017
Link: https://doi.org/10.1016/..
 
?
11

Assessment of the enhanced DHRS configuration for MYRRHA re..:

Bubelis, E. ; Jaeger, W. ; Bandini, G...
Nuclear Engineering and Design.  307 (2016)  - p. 181-187 , 2016
Link: https://doi.org/10.1016/..
 
?
12

Assessment of SFR reactor safety issues. Part I: Analysis o..:

Schikorr, M. ; Bubelis, E. ; Carluec, B..
Nuclear Engineering and Design.  285 (2015)  - p. 249-262 , 2015
Link: https://doi.org/10.1016/..
 
?
13

Extension and validation of SIMMER III code for gas cooled ..:

Chen, X.-N. ; Andriolo, L. ; Rineiski, A....
Annals of Nuclear Energy.  81 (2015)  - p. 320-331 , 2015
Link: https://doi.org/10.1016/..
 
?
14

Code assessment and modelling for Design Basis Accident ana..:

Lazaro, A. ; Schikorr, M. ; Mikityuk, K....
Nuclear Engineering and Design.  277 (2014)  - p. 265-276 , 2014
Link: https://doi.org/10.1016/..
 
?
15

The core design of ALFRED, a demonstrator for the European ..:

Grasso, G. ; Petrovich, C. ; Mattioli, D....
Nuclear Engineering and Design.  278 (2014)  - p. 287-301 , 2014
Link: https://doi.org/10.1016/..
 
1-15