Activation and decay heat analysis of the European DEMO blanket concepts T Eade, M Garcia, R Garcia, F Ogando, P Pereslavtsev, J Sanz, ... Fusion Engineering and Design 124, 1241-1245, 2017 | 34 | 2017 |
Design of a beam dump for the IFMIF-EVEDA accelerator B Branas, D Iglesias, F Arranz, G Barrera, N Casal, M García, J Gómez, ... Fusion Engineering and Design 84 (2-6), 509-513, 2009 | 34 | 2009 |
DEMO–The main achievements of the Pre–Concept phase of the safety and environmental work package and the development of the GSSR G Caruso, S Ciattaglia, B Colling, L Di Pace, DN Dongiovanni, M D'Onorio, ... Fusion Engineering and Design 176, 113025, 2022 | 31 | 2022 |
First IFMIF/EVEDA radioprotection studies for the preliminary design of the accelerator beam dump J Sanz, M García, F Ogando, A Mayoral, D López, P Sauvan, B Brañas Fusion Science and Technology 56 (1), 273-280, 2009 | 31 | 2009 |
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 |
MCNP model of the ITER Tokamak Complex AJ López-Revelles, JP Catalán, A Kolšek, R Juárez, R García, M García, ... Fusion Engineering and Design 136, 859-863, 2018 | 25 | 2018 |
Radiological impact mitigation of waste coming from the European fusion reactor DEMO with DCLL breeding blanket I Palermo, R Garcia, M Garcia, J Sanz Fusion Engineering and Design 124, 1257-1262, 2017 | 13 | 2017 |
Deuteron cross section evaluation for safety and radioprotection calculations of IFMIF/EVEDA accelerator prototype V Blideanu, M García, P Joyer, D López, A Mayoral, F Ogando, F Ortíz, ... Journal of nuclear materials 417 (1-3), 1271-1274, 2011 | 13 | 2011 |
Evaluation of the electroforming technique for IFMIF-EVEDA beam dump manufacturing F Arranz, B Brañas, M Busch, M González, A Muñoz, B Szcepaniak, ... Fusion Science and Technology 60 (2), 538-543, 2011 | 11 | 2011 |
Computational tools and nuclear data for radioprotection studies in low energy light ions accelerators P Sauvan, A Mayoral, J Sanz, F Ogando, M García, D Lopez, AJ Koning, ... Journal of the Korean Physical Society 59 (2), 1195-1198, 2011 | 11 | 2011 |
Neutron induced activation in the EVEDA accelerator materials: Implications for the accelerator maintenance J Sanz, M García, P Sauvan, D López, C Moreno, A Ibarra, L Sedano Journal of nuclear materials 386, 991-993, 2009 | 11 | 2009 |
Integrated design of tokamak building concepts including ex-vessel maintenance C Gliss, C Bachmann, B Drumm, S Ciattaglia, M Garcia, I Moscato, T Mull, ... Fusion Engineering and Design 177, 113068, 2022 | 9 | 2022 |
Sensitivity to nuclear data in the radioprotection design of the LIPAC (IFMIF/EVEDA) Beam Dump M García, F Ogando, P Sauvan, J Sanz, D López, B Brañas Fusion Science and Technology 62 (1), 265-271, 2012 | 9 | 2012 |
Status of reliability in determining SDDR for manual maintenance activities in ITER: quality assessment of relevant activation cross sections involved R Garcia, M Garcia, R Pampin, J Sanz Fusion Engineering and Design 112, 177-191, 2016 | 7 | 2016 |
Optimized design of local shielding for the IFMIF/EVEDA beam dump M García, F Ogando Serrano, P Ortego, JM Arroyo, B Brañas, C Töre, ... Nuclear Energy Agency, Organisation for Economic Co-operation and Development, 2010 | 7 | 2010 |
Decay gamma dose rates in the EVEDA accelerator: impact of the deuteron loss uncertainties in accelerator maintenance M García, J Sanz, P Sauvan, F Ogando, D López, A Mayoral, V Blideanu, ... Nuclear technology 168 (1), 132-138, 2009 | 7 | 2009 |
Methodology to address radiation protection and safety issues in the IFMIF-EVEDA accelerator prototype J Sanz, P Sauvan, F Ogando, D López, M García, A Mayoral, F Ortiz, ... Shielding aspects of accelerators, targets and irradiation facilities-Satif-10, 2010 | 5 | 2010 |
Evaluation of neutron production from dd and other reactions in the EVEDA accelerator prototype (including beam dump) and evaluation of neutron flux. Evaluation of neutron … J Sanz, M García, P Sauvan, D López, M Embid, C Moreno, L Sedano EFDA Task: TW6-TTMI-004, Deliverable 3. Final Report. UNED, 2007 | 5 | 2007 |
Integration of DEMO hazard piping into the tokamak building C Gliss, C Bachmann, S Ciattaglia, M García, G Federici, M Koerber, ... Fusion Engineering and Design 168, 112415, 2021 | 4 | 2021 |
Radiological impact mitigation of waste coming from the European Fusion Reactor DCLL DEMO I Palermo, R García, M García, J Sanz Fusion Engineering and Design, 2016 | 4 | 2016 |