| Lead–lithium eutectic material database for nuclear fusion technology EM De Les Valls, LA Sedano, L Batet, I Ricapito, A Aiello, O Gastaldi, ... Journal of nuclear materials 376 (3), 353-357, 2008 | 242 | 2008 |
| Uncertainty and sensitivity analysis of a LBLOCA in a PWR Nuclear Power Plant: Results of the Phase V of the BEMUSE programme M Perez, F Reventos, L Batet, A Guba, I Tóth, T Mieusset, P Bazin, ... Nuclear Engineering and Design 241 (10), 4206-4222, 2011 | 80 | 2011 |
| Uncertainty and sensitivity analysis of the LOFT L2-5 test: Results of the BEMUSE programme A de Crécy, P Bazin, H Glaeser, T Skorek, J Joucla, P Probst, K Fujioka, ... Nuclear Engineering and Design 238 (12), 3561-3578, 2008 | 76 | 2008 |
| Supercritical CO2 Brayton power cycles for DEMO (demonstration power plant) fusion reactor based on dual coolant lithium lead blanket JI Linares, A Cantizano, BY Moratilla, V Martín-Palacios, L Batet Energy 98, 271-283, 2016 | 53 | 2016 |
| Boron transport model with physical diffusion for RELAP5 J Freixa, F Reventós, C Pretel, L Batet Nuclear Technology 160 (2), 205-215, 2007 | 39 | 2007 |
| SBLOCA with boron dilution in pressurized water reactors. Impact on operation and safety J Freixa, F Reventós, C Pretel, L Batet, I Sol Nuclear Engineering and Design 239 (4), 749-760, 2009 | 38 | 2009 |
| Modelling of integrated effect of volumetric heating and magnetic field on tritium transport in a U-bend flow as applied to HCLL blanket concept EM de Les Valls, L Batet, V De Medina, J Fradera, L Sedano Fusion Engineering and Design 86 (4-5), 341-356, 2011 | 36 | 2011 |
| Recuperated versus single-recuperator re-compressed supercritical CO2 Brayton power cycles for DEMO fusion reactor based on dual coolant lithium lead blanket JI Linares, A Cantizano, E Arenas, BY Moratilla, V Martín-Palacios, L Batet Energy 140, 307-317, 2017 | 31 | 2017 |
| Advanced qualification process of ANAV NPP integral dynamic models for supporting plant operation and control F Reventós, L Batet, C Llopis, C Pretel, M Salvat, I Sol Nuclear Engineering and Design 237 (1), 54-63, 2007 | 28 | 2007 |
| Modelling of a supercritical CO2 power cycle for nuclear fusion reactors using RELAP5–3D L Batet, JM Alvarez-Fernandez, EM de les Valls, V Martinez-Quiroga, ... Fusion Engineering and Design 89 (4), 354-359, 2014 | 26 | 2014 |
| Analysis of the Feed & Bleed procedure for the Ascó NPP: first approach study for operation support F Reventós, L Batet, C Pretel, M Ríos, I Sol Nuclear engineering and design 237 (18), 2006-2013, 2007 | 25 | 2007 |
| Sizing of a recuperative supercritical CO2 Brayton cycle as power conversion system for DEMO fusion reactor based on Dual Coolant Lithium Lead blanket JI Linares, E Arenas, A Cantizano, J Porras, BY Moratilla, M Carmona, ... Fusion Engineering and Design 134, 79-91, 2018 | 24 | 2018 |
| An analytical comparative exercise on the OECD-SETH PKL E2. 2 experiment F Reventós, J Freixa, L Batet, C Pretel, D Luebbesmeyer, D Spaziani, ... Nuclear Engineering and Design 238 (4), 1146-1154, 2008 | 22 | 2008 |
| Design and qualification of an on-line permeator for the recovery of tritium from lead–lithium eutectic breeding alloy G Veredas, J Fradera, I Fernández, L Batet, I Peñalva, L Mesquida, ... Fusion Engineering and design 86 (9-11), 2365-2369, 2011 | 21 | 2011 |
| Numeric implementation of a nucleation, growth and transport model for helium bubbles in lead–lithium HCLL breeding blanket channels: Theory and code development L Batet, J Fradera, EM de les Valls, LA Sedano Fusion engineering and design 86 (4-5), 421-428, 2011 | 17 | 2011 |
| BEMUSE phase V report: Uncertainty and sensitivity analysis of a LBLOCA in Zion nuclear power plant F Reventos, L Batet, M Pérez NEA/CSNI/R (2009) 13, 2009 | 17 | 2009 |
| Adaptación de biodigestores tubulares de plástico a climas fríos D Poggio, I Ferrer Martí, L Batet Miracle, E Velo García Livestock research for rural development 21 (9), 1-14, 2009 | 17 | 2009 |
| Thermal-hydraulic analysis tasks for ANAV NPPs in support of plant operation and control F Reventos, L Batet, C Llopis, C Pretel, I Sol Science and Technology of Nuclear Installations 2008, 2008 | 16 | 2008 |
| Qualification of MHD effects in dual-coolant DEMO blanket and approaches to their modelling EM de les Valls, L Batet, V de Medina, J Fradera, LA Sedano Fusion engineering and design 86 (9-11), 2326-2329, 2011 | 14 | 2011 |
| Implementation of two-phase tritium models for helium bubbles in HCLL breeding blanket modules J Fradera, L Sedano, EM De Les Valls, L Batet Journal of nuclear materials 417 (1-3), 739-742, 2011 | 13 | 2011 |
