E-LIB Suche - Ergebnisse für: Reventos, F.

1

OECD/NEA/CSNI state-of-the-art report on scaling in system ..:

Mascari, F. ; D'Auria, F. ; Bestion, D....
Nuclear Engineering and Design. 416 (2024) - p. 112750 , 2024

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

2

Spanish contribution to the development and application of ..:

Freixa, J. ; Barrachina, T. ; Berna, C....
Nuclear Engineering and Design. 417 (2024) - p. 112837 , 2024

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

3

What is the future for nuclear fission technology? A techni..:

D'Auria, F. ; Reventos, F. ; Herranz, L....
Nuclear Engineering and Design. 425 (2024) - p. 113332 , 2024

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

4

Off-line vs. semi-implicit TH-TH coupling schemes: A BEPU c..:

Casamor, M. ; Avramova, M. ; Reventós, F..
Annals of Nuclear Energy. 178 (2022) - p. 109344 , 2022

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

5

On the validation of BEPU methodologies through the simulat..:

Freixa, J. ; Martínez-Quiroga, V. ; Casamor, M....
Nuclear Engineering and Design. 379 (2021) - p. 111238 , 2021

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

6

On the scaling of uncertainties in thermal hydraulic system..:

Casamor, M. ; Martinez-Quiroga, V. ; Reventós, F...
Annals of Nuclear Energy. 136 (2020) - p. 107026 , 2020

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

7

Modelling guidelines for safety analysis of Station Black O..:

Freixa, J. ; Martinez-Quiroga, V. ; Reventós, F.
Annals of Nuclear Energy. 138 (2020) - p. 107179 , 2020

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

8

Perfecting the use of hybrid models in scaling analysis:

Reventos, F. ; Martinez-Quiroga, V. ; Freixa, J.
Nuclear Engineering and Design. 354 (2019) - p. 110187 , 2019

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

9

PVST, a tool to assess the Power to Volume scaling distorti..:

Martinez-Quiroga, V. ; Freixa, J. ; Reventos, F.
Nuclear Engineering and Design. 332 (2018) - p. 173-185 , 2018

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

10

List of authors:

, In: Thermal-Hydraulics of Water Cooled Nuclear Reactors,

Aksan, N. ; Bestion, D. ; D'Auria, F.... - p. xi , 2017

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

11

Parameters and concepts:

, In: Thermal-Hydraulics of Water Cooled Nuclear Reactors,

Reventos, F. - p. 89-141 , 2017

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

12

Comparison of Best-Estimate Plus Uncertainty and Conservati..:

Pericas, R. ; Ivanov, K. ; Reventós, F..
Nuclear Technology. 198 (2017) 2 - p. 193-201 , 2017

Link: https://doi.org/10.1080/..

13

Code improvement and model validation for Ascó-II Nuclear P..:

Pericas, R. ; Ivanov, K. ; Reventós, F..
Annals of Nuclear Energy. 87 (2016) - p. 366-374 , 2016

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

14

Qualification of a full plant nodalization for the predicti..:

Freixa, J. ; Martínez-Quiroga, V. ; Reventós, F.
Nuclear Engineering and Design. 308 (2016) - p. 115-132 , 2016

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

15

Modelling guidelines for core exit temperature simulations ..:

Freixa, J. ; Martínez-Quiroga, V. ; Zerkak, O..
Nuclear Engineering and Design. 286 (2015) - p. 116-129 , 2015

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