| Objectives and status of EUROfusion DEMO blanket studies LV Boccaccini, G Aiello, J Aubert, C Bachmann, T Barrett, A Del Nevo, ... Fusion Engineering and Design 109, 1199-1206, 2016 | 242 | 2016 |
| Confinement transitions in TJ-II under Li-coated wall conditions J Sánchez, M Acedo, A Alonso, J Alonso, P Alvarez, E Ascasíbar, ... Nuclear Fusion 49 (10), 104018, 2009 | 104 | 2009 |
| The accomplishment of the engineering design activities of IFMIF/EVEDA: the European–Japanese project towards a Li (d, xn) fusion relevant neutron source J Knaster, A Ibarra, J Abal, A Abou-Sena, F Arbeiter, F Arranz, JM Arroyo, ... Nuclear Fusion 55 (8), 086003, 2015 | 87 | 2015 |
| The role of a fast ion component on the heating of the plasma bulk D Rapisarda, B Zurro, V Tribaldos, A Baciero Plasma Physics and Controlled Fusion 49 (3), 309, 2007 | 86 | 2007 |
| Progress in EU Breeding Blanket design and integration F Cismondi, LV Boccaccini, G Aiello, J Aubert, C Bachmann, T Barrett, ... Fusion Engineering and Design 136, 782-792, 2018 | 77 | 2018 |
| Conceptual design of the EU-DEMO dual coolant lithium lead equatorial module D Rapisarda, I Fernandez, I Palermo, M González, C Moreno, A Ibarra, ... IEEE transactions on plasma science 44 (9), 1603-1612, 2016 | 66 | 2016 |
| Progress of the conceptual design of the European DEMO breeding blanket, tritium extraction and coolant purification systems F Cismondi, GA Spagnuolo, LV Boccaccini, P Chiovaro, S Ciattaglia, ... Fusion Engineering and Design 157, 111640, 2020 | 59 | 2020 |
| Overview of TJ-II experiments C Hidalgo, C Alejaldre, A Alonso, J Alonso, L Almoguera, F de Aragón, ... Nuclear fusion 45 (10), S266, 2005 | 58 | 2005 |
| Status of maturation of critical technologies and systems design: Breeding blanket LV Boccaccini, F Arbeiter, P Arena, J Aubert, L Bühler, I Cristescu, ... Fusion Engineering and Design 179, 113116, 2022 | 51 | 2022 |
| Status of the engineering activities carried out on the European DCLL D Rapisarda, I Fernandez, I Palermo, FR Urgorri, L Maqueda, D Alonso, ... Fusion Engineering and Design 124, 876-881, 2017 | 50 | 2017 |
| Design of a permeator against vacuum for tritium extraction from eutectic lithium-lead in a DCLL DEMO B Garcinuno, D Rapisarda, I Fernández, C Moreno, I Palermo, Á Ibarra Fusion Engineering and Design 117, 226-231, 2017 | 46 | 2017 |
| Tritium extraction technologies and DEMO requirements D Demange, R Antunes, O Borisevich, L Frances, D Rapisarda, ... Fusion Engineering and Design 109, 912-916, 2016 | 43 | 2016 |
| Magnetohydrodynamic and thermal analysis of PbLi flows in poloidal channels with flow channel insert for the EU-DCLL blanket FR Urgorri, S Smolentsev, I Fernández-Berceruelo, D Rapisarda, ... Nuclear fusion 58 (10), 106001, 2018 | 41 | 2018 |
| Tritium modelling in HCPB breeder blanket at a system level E Carella, C Moreno, FR Urgorri, D Rapisarda, A Ibarra Fusion Engineering and Design 124, 687-691, 2017 | 40 | 2017 |
| Design and fabrication of a Permeator Against Vacuum prototype for small scale testing at Lead-Lithium facility B Garcinuño, D Rapisarda, I Fernández-Berceruelo, D Jiménez-Rey, ... Fusion Engineering and Design 124, 871-875, 2017 | 35 | 2017 |
| The tritium extraction and removal system for the DCLL-DEMO fusion reactor B Garcinuño, D Rapisarda, R Antunes, M Utili, I Fernández-Berceruelo, ... Nuclear Fusion 58 (9), 095002, 2018 | 33 | 2018 |
| Development of sandwich flow channel inserts for an EU DEMO dual coolant blanket concept P Norajitra, WW Basuki, M Gonzalez, D Rapisarda, M Rohde, L Spatafora Fusion Science and Technology 68 (3), 501-506, 2015 | 31 | 2015 |
| Analysis of displacement damage in materials in nuclear fusion facilities (DEMO, IFMIF and TechnoFusion) F Mota, R Vila, C Ortiz, A Garcia, N Casal, A Ibarra, D Rapisarda, V Queral Fusion Engineering and Design 86 (9-11), 2425-2428, 2011 | 30 | 2011 |
| Integrated design of breeding blanket and ancillary systems related to the use of helium or water as a coolant and impact on the overall plant design GA Spagnuolo, R Arredondo, LV Boccaccini, P Chiovaro, S Ciattaglia, ... Fusion Engineering and Design 173, 112933, 2021 | 27 | 2021 |
| The IFMIF-EVEDA accelerator beam dump design D Iglesias, F Arranz, JM Arroyo, G Barrera, B Brañas, N Casal, M García, ... Journal of Nuclear Materials 417 (1-3), 1275-1279, 2011 | 27 | 2011 |
