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Mauricio García Camacho
Mauricio García Camacho
Postdoctoral Researcher, UNED
Verified email at ind.uned.es - Homepage
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Cited by
Cited by
Year
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
342017
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
342009
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
312022
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
312009
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
272011
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
252018
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
132017
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
132011
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
112011
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
112011
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
112009
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
92022
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
92012
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
72016
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
72010
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
72009
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
52010
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
52007
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
42021
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
42016
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