Results 121 to 130 of about 212 (166)
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Theoretical study of GDM-SA-SVR algorithm on RAFM steel

Artificial Intelligence Review, 2020
With the development of society and the exhaustion of fossil energy, we need to identify new alternative energy sources. Nuclear energy is an ideal choice, but the key to the successful application of nuclear technology is determined primarily by the behavior of nuclear materials in reactors.
Ming Zhao, Sifan Long
exaly   +3 more sources

Development of IN-RAFM steel and fabrication technologies for Indian TBM

Fusion Engineering and Design, 2016
Abstract India has indigenously developed its own Indian Reduced Activation Ferritic Martensitic Steel (IN-RAFM steel) which, it is proposed to use for fabrication of Indian TBM to be installed in ITER. With an objective of qualifying this material for use in ITER, extensive testing of this material to generate the necessary data required to offer ...
K Laha, S K Albert, A K Bhaduri
exaly   +2 more sources

Embrittlement behavior of neutron irradiated RAFM steels

Journal of Nuclear Materials, 2007
Abstract The effects of neutron irradiation on the embrittlement behavior of reduced activation ferritic/martensitic (RAFM) steel EUROFER97 for different heat treatment conditions have been investigated. The irradiation to 16.3 dpa at different irradiation temperatures (250–450 °C) was carried out in the Petten High Flux Reactor in the framework of ...
Gaganidze, E.   +3 more
openaire   +4 more sources

Neutron Irradiation Resistance of RAFM Steels

MRS Proceedings, 2006
AbstractThe neutron irradiation resistance of the reduced-activation ferritic/martensitic (RAFM) steel EUROFER97 and international reference steels (F82H-mod, OPTIFER-Ia, GA3X and MANET-I) have been investigated after irradiation in the Petten High Flux Reactor up to 16.3 dpa at different irradiation temperatures (250-450 ¡ãC).
Gaganidze, E., Dafferner, B., Aktaa, J.
openaire   +1 more source

Annealing Behavior of RAFM ODS-Eurofer Steel

Fusion Science and Technology, 2012
Oxide-dispersion-strengthened ~ODS! ferritic-martensitic steels are potential candidates for severalapplications including the manufacture of structural partsfor nuclear fusion technology. Because of their moder-ate creep properties, non-ODS reduced-activation ferritic-martensitic ~RAFM!
Sandim, H. R. Z.   +5 more
openaire   +2 more sources

Assessment of neutron irradiation effects on RAFM steels

Fusion Engineering and Design, 2013
Abstract The objective of the current work is assessment of the effects of neutron irradiation on the mechanical properties of blanket and divertor materials of a future fusion energy generation Demonstration Power Plant (DEMO). The emphasis is put on the review of the tensile, Charpy impact and fracture toughness properties of EUROFER97 and EUROFER ...
Gaganidze, E., Aktaa, J.
openaire   +2 more sources

Modeling of Creep Deformation Behaviour of RAFM Steel

Transactions of the Indian Institute of Metals, 2016
Creep tests were carried out on reduced activation ferritic–martensitic steel at 773, 823 and 873 K. Creep strain–time trajectory obtained was subsequently modeled by 4-theta projection methodology. An optimum cutoff strain was defined in tertiary regime for better representation of creep curves.
V. S. Srinivasan   +3 more
openaire   +1 more source

Study the erosion of RAFM steels with the linear plasma device GyM [PDF]

open access: possible, 2021
The use of bare reduced activation ferritic martensitic (RAFM) steels, like Eurofer-97, has recently been envisaged as a possible option for the recessed elements of the first-wall of DEMO. The erosion by hydrogenic charge-exchange neutrals (CXNs) can significantly affect the lifetime of these components and needs to be assessed properly [1].
Uccello A   +12 more
openaire   +2 more sources

Manufacturing of ODS RAFM Steel: Mechanical and Microstructural Characterization

Materials Science Forum, 2016
Ferritic ODS 14Cr steels reinforced by means of Yttrium oxide nanoclusters represent one of the options for future structural applications in nuclear Generation IV reactors. Due to their high tensile properties and resistance to irradiation damage, Oxide Dispersion Strengthened Steels (ODS-S) have been suggested for nuclear fusion applications.
Claudio Testani   +2 more
openaire   +1 more source

Mechanical and microstructural properties of a hipped RAFM ODS-steel

Journal of Nuclear Materials, 2002
Abstract Oxide dispersion strengthened (ODS) materials for structural applications in future fusion power reactors would allow to increase the operating temperature to approximately 650 °C. Two ODS variants of the 9%CrWVTa-RAFM steel EUROFER 97 with Y2O3 contents of 0.3 and 0.5 wt% have been produced.
Lindau, R.   +4 more
openaire   +2 more sources

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