T. Hernandez
Complutense University of Madrid
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Featured researches published by T. Hernandez.
symposium on fusion technology | 2003
T. Hernandez; A. Moroño; E.R. Hodgson
Abstract High quality mirrors will be required for different diagnostic and remote handling systems in International Thermonuclear Experimental Reactor (ITER). The possibility of radiation enhanced surface degradation has been assessed. Unprotected Duralumin discs and high quality SiO overcoated aluminium on Pyrex mirrors have been irradiated with 60 Co gamma rays at 12 Gy/s up to 50 MGy. Irradiations from 303 to 523 K have been performed in air and nitrogen. It has been observed that humidity is a key factor in the degradation process and produces severe corrosion on the aluminium mirror surface even with SiO overcoating. SEM and XPS analysis of chemical species formed on the surface indicate that the degradation produces aluminium hydroxide compounds, and the corrosion corresponds to a filiform mechanism.
IEEE Transactions on Plasma Science | 2018
Francisco Andrés León Hernández; Frederik Arbeiter; Lorenzo V. Boccaccini; Evaldas Bubelis; V. Chakin; Ion Cristescu; Bradut E. Ghidersa; María Asenjo González; Wolfgang Hering; T. Hernandez; Xue Z. Jin; Marc Kamlah; B. Kiss; Regina Knitter; M.H.H. Kolb; P. Kurinskiy; Oliver Leys; Ivan Alessio Maione; Marigrazia Moscardini; Gabor Nadasi; Heiko Neuberger; P. Pereslavtsev; Simone Pupeschi; R. Rolli; Sebastian Ruck; Gandolfo Alessandro Spagnuolo; P. Vladimirov; Christian Zeile; Guangming Zhou
In the framework of the EUROfusion’s Power Plant Physics and Technology, the working package breeding blanket (BB) aims at investigating four different BB concepts for an EU demonstration fusion reactor (DEMO). One of these concepts is the helium-cooled pebble bed (HCPB) BB, which is based on the use of pebble beds of lithiated ternary compounds and Be or beryllides as tritium breeder and multiplier materials, respectively, EUROFER97 as structural steel and He as coolant. This paper aims at giving an overview of the EU HCPB BB Research and Development (R&D) being developed at KIT, in collaboration with Wigner-RCP, BUTE-INT, and CIEMAT. The paper gives an outline of the HCPB BB design evolution, state-of-the-art basic functionalities, requirements and performances, and the associated R&D activities in the areas of design, functional materials, manufacturing, and testing. In addition, attention is given also to the activities dedicated to the development of heat transfer augmentation techniques for the first wall and the corresponding testing. Due to their nature as design drivers, a brief overview in the R&D of key HCPB interfacing areas is given as well, namely, the tritium extraction and recovery system, the primary heat transfer and power conversion systems, and safety topics, as well as some specific activities regarding the integration of in-vessel systems through the BB. As concluding remarks, an outline of the standing challenges and future R&D plans is summarized.
Journal of Nuclear Materials | 2011
E.R. Hodgson; M. Malo; J. Manzano; A. Moroño; T. Hernandez
Journal of Alloys and Compounds | 2008
T. Hernandez; P. Martín
symposium on fusion technology | 2009
A. Moroño; R. Vila; T. Hernandez; J. Manzano; E.R. Hodgson
Fusion Engineering and Design | 2014
T. Hernandez; A. Moroño; E.R. Hodgson; M. Malo; M. Verdú; F.J. Sánchez.
symposium on fusion technology | 2005
T. Hernandez; A. Moroño; E.R. Hodgson
Fusion Engineering and Design | 2015
Elisabetta Carella; T. Hernandez
Journal of Nuclear Materials | 2014
T. Hernandez; P. Fernández
Journal of Nuclear Materials | 2014
T. Hernandez; P. Fernández; R. Vila