N.C.S.R. "DEMOKRITOS" - FUSION TECHNOLOGY RESEARCH TEAM

Tuesday, 28 December 2010 14:59 | Print
demokritos

N.C.S.R. "DEMOKRITOS"
 INSTITUTE OF NUCLEAR TECHNOLOGY AND RADIATION PROTECTION
Fusion Technology Research Team

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Scientific Responsible: K. Mergia
Address: N.C.S.R. "Demokritos", 153 10 Agia Paraskevi Attiki, Greece
Telephone: +30 210 650 3706
Fax: +30 210 650 3766
e-mail: This e-mail address is being protected from spambots. You need JavaScript enabled to view it

Staff:
• G. Apostolopoulos Research Scientist C'
• E. Devlin Research Scientist A'
• Μ. Gjoka Research Officer
• P. Grammatikopoulos Post Doc
• S. Harissopoulos Research Scientist A'
• Z. Kotsina PhD Student
• T. Lagoyannis Research Scientist C'
• Κ. Μergia Research Scientist B'
• S. Μessoloras Research Scientist A'
• K. Papamichail PhD Student
• M. Pissas Research Scientist A'
• Th. Speliotis Research Officer
• Ι. Stamatelatos Research Scientist A'
• D. Vassilopoulou PhD Student
 
Scientific Interests:
• Radiation damage effects in fusion related materilas.
• Physical and magnetic properties of fusion materials.
• Superconductive materials for fusion applications.
• Advanced materials for fusion and fission applications.
• Induced activity evaluation.
• Neutron irradiation experiments under control environment conditions.
• Simulation of reactor irradiation facilities.
• Remote evaluation of radioactive contamination of fusion device components.
 
Publications in Fusion:
• M. Pissas, M. Zeibekis, D. Stamopoulos, Chunlei Wang, Yanwei Ma, “Irreversibility line of Ba1xKxFe2As2 (Tc = 36.9 K) superconductor studied with ac-susceptibility measurements”, Physica C 476 (2012) 68-72
• Vasilopoulou T., Tzika F., Stamatelatos I.E., "Collimated scanning for large sample neutron activation analysis of inhomogeneous samples", J Radioanal Nucl Chem 291 (2012) 479–483
• G. Apostolopoulos, K. Mergia, S. Messoloras, and A. Lagoyannis, “Resistivity recovery of proton irradiated Fe-Cr alloys”, 13th International Workshop on Plasma-Facing Materials and Components for Fusion Applications, 9-13 May 2011, Rosenheim, Germany
• M. Kastriotou, M. Grattarola, C. Gualco, M. Hofmann, B. Schillinger,
S. Messoloras and K. Mergia, “Residual Stress Measurements of a CuCrZr Tube Brazed to a Tungsten Tile Using Neutron Diffraction”, 13th International Workshop on Plasma-Facing Materials and Components for Fusion Applications and 1st Fusion Energy Materials Science Workshop, 9-13 May 2011, Rosenheim, Germany
• K. Mergia, M. Grattarola, C. Gualco, S. Messoloras and M. Hofmann, “Residual Stress Measurements on Mo/Cu and Mo/CuCrZr tiles using neutron diffraction”, Advanced Materials Research, 59, 299-303 (2009)
• K. Mergia and N. Boukos, “Structural, thermal, electrical and magnetic properties of Eurofer 97 steel”, J. Nucl. Mater. 373 (2008)
• Lucon E, Benoit P, Jacquet P, Diegele E, Lasser R, Alamo A, Coppola R, Gillemot F, Jung P, Lind A, Messoloras S, Novosad P, Lindau R, Preininger D, Klimiankou M, Petersen C, Rieth M, Materna-Morris E, Schneider HC, Rensman JW, van der Schaaf B, Singh BK, Spaetig P, “The European effort towards the development of a demo structural material: Irradiation behaviour of the European reference RAFM steel EUROFER”, FUSION ENGINEERING AND DESIGN 81 (8-14): 917-923 (2006)
• A. -A. F. Tavassoli, A. Alamo, L. Bedel, L. Forest, J. -M. Gentzbittel, J. -W. Rensman, E. Diegele, R. Lindau, M. Schirra, R. Schmitt, H.C. Schneider, C. Petersen, A.-M. Lancha, P. Fernandez, G. Filacchioni, M.F. Maday, K. Mergia, N. Boukos, Baluc, P. Spatig, E. Alves, E. Lucon, “Materials design data for reduced activation martensitic steel type EUROFER”,  Journal of Nuclear Materials, 329-333, 257-262 (2004)
• I.E. Stamatelatos, K. Mergia, G. Lefkopoulos and R. Forrest, “Impurities and Evaluation of induced activity of SiCf/SiC composites”, Nucl. Instrum. & Meth. Phys. Res. B 213, 511-514 (2004)
• K. Mergia, M. Gjoka, D. Niarchos, S. Messoloras and A. Peacock, “Magnetic and electric properties of AISI 430 Ferritic Stainless Steels”, Proccedings of the European Congress on Advanced Materials and Processes, Prague, 5-8 September 2005
 
Annual Reports:
• Annual Report 2002 3a1) Radiation resistance of SiCf/SiC composites and SiC fibres
3a2) Synthesis of SiC and in-situ bonding of SiCf/SiC by rapid combustion processing
3b1) Impurity determination of advanced SiC fibers and validation of European Activation Data
3b2) Neutron irradiation up to 0.8 dpa at 200-250°C of EUROFER plates
3b3) Tungsten: preliminary experiment
3b4) Thermal, electrical and ferro-magnetic properties of standard Eurofer plate
3b5) Complete EUROFER characterisation of the typical microstructures and modelling of the phase transformation behaviour

• Annual Report 2003
 2b) Diagnostics and modelling of boundary layer plasmas and wall effects
3a1) Structure evolution of SiCSiC composites under neutron irradiation
3b1) Detailed metallurgical characterisation (including ageing effects) of the EU ODS steel
3b2) Morphological characterisation of SiC/SiC composite: fibres, interface, matrix and porosities
3b3) Development of Joining techniques for SiC/SiC
3b4) Validation experiments for selected EFF/EAF data evaluations (E<20 MeV): Measurements and analysis of gamma activation in EUROFER irradiated in low energy (fission) neutron spectrum
3b5) Neutron irradiation up to 0.8 dpa at 200-250°C of EUROFER plates
3b6) Tungsten: preliminary experiment
3b7) Thermal, electrical and ferro-magnetic properties of standard Eurofer plate
3b8) Complete EUROFER characterisation of the typical microstructures and modelling of the phase transformation behaviour
• Annual Report 2004 3a1) Tough, layered SiC-based composites, using SiC needle-like powders made by combustion synthesis
3a2) Gas impermeable coatings for SiCf/SiC
3a3) Structure evolution of SiCSiC composites under neutron irradiation
3b1) Detailed metallurgical characterisation (including ageing effects) of the EU ODS steel
3b2) Morphological characterisation of SiC/SiC composite: fibres, interface, matrix and porosities
3b3) Neutron irradiation up to 0.8 dpa at 200-250°C of EUROFER plates
3b4) Measurement of the magnetic properties of ITER vacuum vessel materials and welds
• Annual Report 2005 3a1) Tough, layered SiC-based composites, using SiC needle-like powders made by combustion synthesis (Principal Investigators: G. Vekinis, K. Mergia)
3a2) Gas impermeable coatings for SiCf/SiC (Principal Investigators: G. Vekinis, K. Mergia)
3a3) Structure evolution of SiCfSiC composites under neutron irradiation (Principal Investigator: K. Mergia)
3b1) Detailed metallurgical characterisation (including ageing effects) of the EU ODS steel (TW3_TTMS_006-deliverable 2, Principal Investigator: K.Mergia)
3b2) Morphological characterisation of SiC/SiC composite: fibres, interface, matrix and porosities (TW3_TTMA_001- deliverable 1, Principal Investigator: G.Vekinis)
3b3) Neutron irradiation up to 0.8 dpa at 200-250°C of EUROFER plates (TW2_TTMS_001b_deliverable 7, Principal Investigator: S. Messoloras)
• Annual Report 2006 3a1) Measurement of the structural and magnetic properties of ITER vacuum vessel materials after heat treatments
3a2) Measurement of the structural and magnetic properties of ITER vacuum vessel materials after irradiation
3b1) Detailed metallurgical characterisation (including ageing effects) of the EU ODS steel (TW3_TTMS_006-deliverable 2)
3b2) Neutron irradiation up to 0.8 dpa at 200-2500 C of EUROFER plates (TW2_TTMS_001b_deliverable 7)
• Annual Report 2007 4.1 Microstructure, magnetic, thermal and electrical properties of Fe-Cr alloys
5.1 Detailed metallurgical characterisation (including ageing effects) of the EU ODS steel (TW3 TTMS 006-deliverable 2)
• Annual Report 2008 4.1.1. Understanding of the radiation damage in Fe-Cr steels
4.1.3. Development of radiation resistant coatings
4.1.4. Development of irradiation processes
4.4.1. Development of high and low Tc superconductor hybrid metamaterials
4.6.1 Waste assessment and management procedure determination
• Annual Report 2009 4.1.1. Understanding of the radiation damage in Fe-Cr steels
4.1.3. Development of radiation resistant coatings
4.1.4. Development of irradiation processes (Optimisation of the neutron field characteristics of the new GRR1 LEU core for fusion material irradiation studies)
4.4.1. Development of high and low Tc superconductor hybrid metamaterials (Metamaterial fabrication consisting from layers of high and low Tc superconductors)
4.6.1 Waste assessment and management procedure determination (Optimisation of the design of a gamma spectrometry system to be used for remote evaluation of induced activity at components of a future fusion device for Waste Management purposes.)
• Annual Report 2010
 4.1.1. Understanding of the radiation damage in Fe-Cr steels
4.1.3. Development of radiation resistant coatings
4.1.4. Development of irradiation processes (Optimisation of the neutron field characteristics of the new GRR1 LEU core for fusion material irradiation studies)
4.4.1. Development of high and low Tc superconductor hybrid metamaterials (Metamaterial fabrication consisting from layers of high and low Tc superconductors)
4.6.1 Waste assessment and management procedure determination (Optimisation of the design of a gamma spectrometry system to be used for remote evaluation of induced activity at components of a future fusion device for Waste Management purposes.)
 
Team's website

Last Updated (Tuesday, 06 November 2012 09:16)