Results 101 to 110 of about 91,711 (137)
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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

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.
Sifan Long, Ming Zhao 0007
openaire   +2 more sources

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

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

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

Effects of tantalum on austenitic transformation kinetics of RAFM steel

Journal of Iron and Steel Research International, 2017
The RAFM (reduced activation ferritic/martensitic) steels containing different tantalum contents (0 wt. %, 0.027 wt. %, 0.073 wt. %) were designed and cast. Differential scanning calorimetry and optical microscopy were employed to explore the influence of tantalum content on the austenitic transformation of RAFM steels.
Jian-guo Chen   +4 more
openaire   +1 more source

Solubility of uranium at very low concentration in RAFM steel

Journal of Nuclear Materials, 2002
Abstract In this work we present the results to develop standards of reduced activation ferritic–martensitic (RAFM) alloys for the quantitative determination of uranium in these materials. The results show that a very low efficiency can be obtained during alloying of uranium due to the segregation to the slags. The solubility of U can be increased by
A. Paúl   +3 more
openaire   +1 more source

Effect of Nanostructured Surface on the Corrosion Behavior of RAFM Steels

Oxidation of Metals, 2019
This study investigated the effect of a preformed nanostructured surface on the corrosion behavior of 9Cr2WVTa reduced activation ferritic/martensitic (RAFM) steel and 9Cr+AlSi steel (9Cr2WVTa with the 0.12 wt.% Al and 0.68 wt.% Si addition) at 700 °C in air and at 550 °C in liquid lead–bismuth eutectic (LBE) alloys.
Yanhong Lu   +4 more
openaire   +1 more source

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 ...
S.K. Albert   +4 more
openaire   +1 more source

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