Results 81 to 90 of about 541 (111)

Experimental electronic stopping cross-section of EUROFER97 for slow protons, deuterons and helium ions

Radiation Physics and Chemistry
The experimental electronic stopping cross-section of EUROFER97 for slow protons, deuterons and helium ions is deduced from backscattering experiments from ultrathin film stacks redeposited by magnetron sputtering from bulk EUROFER97 and tungsten on ...
Eduardo Pitthan, Daniel Primetzhofer, Jila Shams-Latifi   +2 more
exaly   +2 more sources

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Post-irradiation annealing of neutron-irradiated EUROFER97

Journal of Nuclear Materials, 2021
Abstract Recent post-irradiation annealing (PIA) investigations on the neutron-irradiated reduced-activation ferritic-martensitic (RAFM) steel EUROFER97 have led to an almost complete recovery of the mechanical properties. To identify responsible microstructural processes, transmission electron microscopy (TEM) investigations on neutron-irradiated ...
Chauhan, Ankur, Yuan, Qian, Dethloff, Christian, Gaganidze, Ermile, Aktaa, Jarir   +4 more
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Investigation on the diffusion bonding of tungsten and EUROFER97

Journal of Nuclear Materials, 2011
Abstract Due to its advantages, tungsten is selected as armor and structural material for use in future fusion power plants. To apply tungsten as structural material, a joint to EUROFER97 is foreseen in current divertor design for which the diffusion bonding is considered in this work.
Basuki, W. W., Aktaa, J.
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Irradiation response of ODS Eurofer97 steel

Journal of Nuclear Materials, 2012
Abstract Oxide dispersion strengthened (ODS) Eurofer97 steel (EU batch, 0.3 wt.% of Y2O3 particles), produced by mechanical alloying followed by hot rolling, is irradiated in the High Flux Reactor in Petten, The Netherlands at three different irradiation temperatures (300, 450 and 550 °C) up to nominal doses of 1 dpa and 3 dpa.
N.V. Luzginova, H.S. Nolles, P. ten Pierick, T. Bakker, R.K. Mutnuru, M. Jong, D.T. Blagoeva   +6 more
openaire   +1 more source

Oxidation behaviour of CVD and electroplated Al-base coatings for EUROFER97

Nuclear Materials and Energy
The reduced activation ferritic/martensitic (RAF/M) EUROFER97 is the primary candidate for coolant-facing alloys of the European DEMO reactor. However, EUROFER97 will face harsh environment, and it might experience enhanced degradation due to the ...
Liberato Volpe, Eric Prestat, Sérgio Lozano-Perez   +2 more
exaly   +2 more sources

Embrittlement of RAFM EUROFER97 by implanted hydrogen

Journal of Nuclear Materials, 2004
About 380 μm thick specimens of low-activation martensitic stainless steel EUROFER97 were homogeneously implanted with protons below about 70 °C to concentrations up to about 1200 appm. Tensile tests were performed at 25 and 200 °C. The tests at 25 °C showed an increase of yield stress and ultimate tensile strength and a decrease of uniform elongation ...
C. Liu, H. Klein, P. Jung
openaire   +1 more source

Irradiation-induced stress relaxation of Eurofer97 steel

Journal of Nuclear Materials, 2011
Abstract The irradiation-induced stress relaxation behavior of Eurofer97 at 300 °C up to 3.4 dpa and under pre-stress loads typical for the ITER applications is investigated. The bolt specimens are pre-loaded from 30% to 90% of the yield strength. To verify the results obtained with the pre-stressed bolts, bent strips were investigated as well.
N.V. Luzginova, M. Jong, J.W. Rensman, J.B.J. Hegeman, J.G. van der Laan   +4 more
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Corrosion susceptibility of EUROFER97 in lithium ceramics breeders

Journal of Nuclear Materials, 2014
Abstract EUROFER97 specimens were exposed in vacuum to lithium silicate pebbles at 550 °C for up to 2880 h, to evaluate its corrosion susceptibility in a simulated breeder blanket environment. The specimens and pebble bed were then analyzed and characterized by SEM-EDX, XRD, and HR-TEM.
Teresa Hernández, Pilar Fernández, Rafael Vila   +2 more
openaire   +1 more source

Ageing Behaviour of Neutron/Irradiated Eurofer97

2017
Eurofer97 is a candidate structural material for nuclear fusion reactors. To better understand the ageing effects due to radiation during long-term use in real fusion conditions, Eurofer97 was neutron irradiated at the High Flux Reactor in The Netherlands. TEM images of post-irradiation Eurofer97 reveal a high density of irradiation-induced dislocation
I. Carvalho, A. Fedorov, M. Kolluri, N. Luzginova, H. Schut, J. Sietsma   +5 more
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Post-irradiation mechanical properties of three EUROFER97 joints

Fusion Engineering and Design, 2008
Abstract Within the development of reduced activation ferritic martensitic (RAFM) steels as prominent structural materials for future fusion reactors, EUROFER97 has recently emerged in Europe as the reference material for the DEMO design. In order to characterise the in-service performance of EUROFER97 as structural material, it is important to ...
Enrico Lucon, W Vandermeulen
exaly   +2 more sources