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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Sand, Andreea E.

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Aalto University

in Cooperation with on an Cooperation-Score of 37%

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Publications (7/7 displayed)

  • 2023Microstructure of a heavily irradiated metal exposed to a spectrum of atomic recoils26citations
  • 2019Relaxation volumes of microscopic and mesoscopic irradiation-induced defects in tungsten44citations
  • 2019Atomistic-object kinetic Monte Carlo simulations of irradiation damage in tungsten18citations
  • 2018A multi-scale model for stresses, strains and swelling of reactor components under irradiation76citations
  • 2018Unusual irradiation-induced disordering in Cu3Au near the critical temperature1citations
  • 2018A model of defect cluster creation in fragmented cascades in metals based on morphological analysis17citations
  • 2018Defect structures and statistics in overlapping cascade damage in fusion-relevant bcc metals59citations

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Mason, Daniel R.
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Boleininger, Max
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Dudarev, Sergei L.
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Nguyen-Manh, Duc
1 / 11 shared
Marinica, Mihai-Cosmin
1 / 8 shared
Alexander, Rebecca
1 / 3 shared
Mason, D. R.
1 / 3 shared
Dudarev, S. L.
1 / 9 shared
Ma, Pui-Wai
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Tarleton, Edmund
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Kirk, Marquis A.
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Bellon, Pascal
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Backer, A. De
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Becquart, C. S.
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Nordlund, Kai
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Domain, C.
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Byggmästar, Jesper
1 / 16 shared
Zitting, A.
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Co-Authors (by relevance)

  • Mason, Daniel R.
  • Boleininger, Max
  • Dudarev, Sergei L.
  • Nguyen-Manh, Duc
  • Marinica, Mihai-Cosmin
  • Alexander, Rebecca
  • Mason, D. R.
  • Dudarev, S. L.
  • Ma, Pui-Wai
  • Tarleton, Edmund
  • Kirk, Marquis A.
  • Bellon, Pascal
  • Lear, Calvin Robert
  • Averback, Robert S.
  • Luneville, L.
  • Simeone, D.
  • Backer, A. De
  • Becquart, C. S.
  • Nordlund, Kai
  • Domain, C.
  • Byggmästar, Jesper
  • Zitting, A.
OrganizationsLocationPeople

article

Relaxation volumes of microscopic and mesoscopic irradiation-induced defects in tungsten

  • Sand, Andreea E.
  • Nguyen-Manh, Duc
  • Mason, Daniel R.
  • Marinica, Mihai-Cosmin
  • Alexander, Rebecca
  • Dudarev, Sergei L.
Abstract

International audience ; The low energy structures of irradiation-induced defects in materials have been extensively studied overseveral decades, as these determine the available modes by which a defect can diffuse or relax, and how themicrostructure of an irradiated material evolves as a function of temperature and time. Consequently manystudies concern the relative energies of possible defect structures, and empirical potentials are commonlyfitted to, or evaluated with respect to these. But recently [Dudarev et al. Nuclear Fusion 2018], we haveshown that other parameters of defects not directly related to defect energies, namely their elastic dipoletensors and relaxation volumes, determine the stresses, strains and swelling of reactor components underirradiation. These elastic properties of defects have received comparatively little attention. In this studywe compute relaxation volumes of irradiation-induced defects in tungsten using empirical potentials, andcompare to density functional theory results. Different empirical potentials give different results, but someclear potential-independent trends can be identifed. We show that the relaxation volume of a small defectcluster can be predicted to within 10% from its point-defect count. For larger defect clusters we provideempirical fits as a function of defect cluster size. We demonstrate that the relaxation volume associated witha single primary-damage cascade can be estimated from the primary knock-on atom energy. We concludethat while annihilation of defects invariably reduces the total relaxation volume of the cascade debris, thereis still no conclusive verdict about whether coalescence of defects reduces or increases the total relaxation volume.

Topics
  • density
  • impedance spectroscopy
  • cluster
  • theory
  • mass spectrometry
  • defect
  • density functional theory
  • tungsten
  • defect structure