Materials Map

Discover the materials research landscape. Find experts, partners, networks.

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The Materials Map is an open tool for improving networking and interdisciplinary exchange within materials research. It enables cross-database search for cooperation and network partners and discovering of the research landscape.

The dashboard provides detailed information about the selected scientist, e.g. publications. The dashboard can be filtered and shows the relationship to co-authors in different diagrams. In addition, a link is provided to find contact information.

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The Materials Map is still under development. In its current state, it is only based on one single data source and, thus, incomplete and contains duplicates. We are working on incorporating new open data sources like ORCID to improve the quality and the timeliness of our data. We will update Materials Map as soon as possible and kindly ask for your patience.

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in Cooperation with on an Cooperation-Score of 37%

Topics

Publications (9/9 displayed)

  • 2023Dislocation density transients and saturation in irradiated zirconium14citations
  • 2023Dislocation density transients and saturation in irradiated zirconium14citations
  • 2019Atomistic-object kinetic Monte Carlo simulations of irradiation damage in tungsten18citations
  • 2017The Effect of Electronic Structure on the Phases Present in High Entropy Alloys60citations
  • 2013Recent progress in research on tungsten materials for nuclear fusion applications in Europe687citations
  • 2013Recent progress in research on tungsten materials for nuclear fusion applications in Europe687citations
  • 2011Review on the EFDA programme on tungsten materialscitations
  • 2009The EU programme for modelling radiation effects in fusion reactor materials77citations
  • 2009Fe-Cr-V ternary alloy-based ferritic steels for high- and low-temperature applicationscitations

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Chart of shared publication
Frankel, Philipp
1 / 73 shared
Ungar, Tamas
2 / 11 shared
Lienert, Ulrich
2 / 29 shared
Zilahi, Gyula
2 / 9 shared
Thomas, Rhys
2 / 37 shared
Koç, Ömer
1 / 5 shared
Race, Christopher P.
1 / 17 shared
Boleininger, Max
2 / 3 shared
Ribárik, G.
2 / 5 shared
Warwick, Andrew
1 / 1 shared
Hegedues, Zoltan
2 / 9 shared
Race, C.
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Preuss, M.
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Koç, Ö.
1 / 1 shared
Warwick, Andrew R.
1 / 1 shared
Frankel, P.
1 / 18 shared
Sand, Andreea E.
1 / 7 shared
Mason, D. R.
1 / 3 shared
Nguyen-Manh, D.
4 / 17 shared
Wrobel, J. S.
1 / 1 shared
Todd, I.
1 / 37 shared
Leong, Z.
1 / 7 shared
Goodall, R.
1 / 32 shared
Nordlund, K.
3 / 23 shared
Rieth, Michael
2 / 58 shared
Vicente, S. M. Gonzalez De
1 / 1 shared
Caturla, M. J.
1 / 1 shared
Mrovec, M.
1 / 16 shared
Swygenhoven, H. Van
1 / 8 shared
Derlet, P. M.
1 / 12 shared
Wallenius, J.
1 / 1 shared
Perlado, M.
1 / 1 shared
Malerba, L.
1 / 8 shared
Lässer, R.
1 / 1 shared
Willaime, F.
1 / 5 shared
Terentyev, D.
1 / 43 shared
Schäublin, R.
1 / 4 shared
Fu, C.-C.
1 / 3 shared
Boutard, J.-L.
1 / 2 shared
Lavrentiev, M. Y.
1 / 3 shared
Weygand, D.
1 / 40 shared
Fivel, M.
1 / 8 shared
Boutard, J. L.
1 / 1 shared
Chart of publication period
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2019
2017
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Co-Authors (by relevance)

  • Frankel, Philipp
  • Ungar, Tamas
  • Lienert, Ulrich
  • Zilahi, Gyula
  • Thomas, Rhys
  • Koç, Ömer
  • Race, Christopher P.
  • Boleininger, Max
  • Ribárik, G.
  • Warwick, Andrew
  • Hegedues, Zoltan
  • Race, C.
  • Preuss, M.
  • Koç, Ö.
  • Warwick, Andrew R.
  • Frankel, P.
  • Sand, Andreea E.
  • Mason, D. R.
  • Nguyen-Manh, D.
  • Wrobel, J. S.
  • Todd, I.
  • Leong, Z.
  • Goodall, R.
  • Nordlund, K.
  • Rieth, Michael
  • Vicente, S. M. Gonzalez De
  • Caturla, M. J.
  • Mrovec, M.
  • Swygenhoven, H. Van
  • Derlet, P. M.
  • Wallenius, J.
  • Perlado, M.
  • Malerba, L.
  • Lässer, R.
  • Willaime, F.
  • Terentyev, D.
  • Schäublin, R.
  • Fu, C.-C.
  • Boutard, J.-L.
  • Lavrentiev, M. Y.
  • Weygand, D.
  • Fivel, M.
  • Boutard, J. L.
OrganizationsLocationPeople

document

Fe-Cr-V ternary alloy-based ferritic steels for high- and low-temperature applications

  • Rieth, Michael
  • Dudarev, S. L.
  • Boutard, J. L.
Abstract

    2EURATOM/UKAEA Fusion Association, Culham Science Centre, Abingdon, Oxfordshire OX14 3DB, UK   The phase stability of alloys and steels developed for application in nuclear fission and fusion technology is one of the decisive factors determining the potential range of operating temperatures and radiation conditions that the core elements of a power plant can tolerate. In the case of ferritic and ferritic-martensitic steels, the choice of the chemical composition is dictated by the phase diagram for binary FeCr alloys where in the 0-9% range of Cr composition the alloy remains in the solid solution phase at and below the room temperature. For Cr concentrations exceeding 9% the steels operating at relatively low temperatures are therefore expected to exhibit the formation of a´ Cr-rich precipitates. These precipitates form obstacles for the propagation of dislocations, impeding plastic deformation and embrittling the material. This sets the low temperature limit for the use of of high (14% to 20%) Cr steels, which for the 20% Cr steels is at approximately 600°C. On the other hand, steels containing 12% or less Cr cannot be used at temperatures exceeding ~600°C due to the occurrence of the a-g transition (912°C in pure iron and 830°C in 7% Cr alloy ), which weakens the steel in the high temperature limit [1,2]. In this study, we investigate the physical properties of a concentrated ternary alloy system that attracted relatively little attention so far. The phase diagram of ternary Fe-Cr-V alloy shows no phase boundaries within a certain broad range of Cr and V concentrations. This makes the alloy sufficiently resistant to corrosion and suggests that steels and dispersion strengthened materials based on this alloy composition may have better strength and stability at high temperatures. Experimental heats were produced on a laboratory scale by arc melting the material components to pellets, then by melting the pellets in an induction furnace and casting the melt into copper moulds. The compositions in weight percent (iron base) are 10Cr5V, 10Cr10V, 10Cr15V, 10Cr10V0.2C, 10Cr10V0.4C. Tensile specimens have been fabricated, heat treated at 1100°C for 2 hours for normalization, and tested at temperatures up to 700°C. The investigations were completed by hardness tests, metallographic imaging, and microstructure analysis. The content of intermetallic (Laves) phases increases with the vanadium content and the addition of carbon leads to carbide (VC) precipitation at the grain boundaries. In general, typical ferritic microstructures are recognizable with huge grain sizes (several 100 µm) for the 10Cr5-15V alloys and with smaller grain sizes (about 50 µm) for the 10Cr10V0.2-0.4C alloys. However, the tensile tests performed so far have indicated about the same strength level at 700 °C.   [1] R. Lindau et al., Fusion Eng. Design (2005) 75-79, 989-996 [2] S.P. Fitzgerald et al., Proc. Royal Soc. London A (2008) 464, 2549–2559 

Topics
  • impedance spectroscopy
  • dispersion
  • polymer
  • Carbon
  • grain
  • corrosion
  • grain size
  • melt
  • laser emission spectroscopy
  • strength
  • carbide
  • steel
  • hardness
  • dislocation
  • copper
  • precipitate
  • precipitation
  • casting
  • iron
  • intermetallic
  • phase diagram
  • vanadium
  • alloy composition
  • phase stability