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%

Topics

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
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Marinica, Mihai-Cosmin
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Alexander, Rebecca
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Mason, D. R.
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Dudarev, S. L.
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Ma, Pui-Wai
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Tarleton, Edmund
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Kirk, Marquis A.
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Nordlund, Kai
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Domain, C.
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Byggmästar, Jesper
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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

A multi-scale model for stresses, strains and swelling of reactor components under irradiation

  • Sand, Andreea E.
  • Ma, Pui-Wai
  • Mason, Daniel R.
  • Tarleton, Edmund
  • Dudarev, Sergei L.
Abstract

Predicting strains, stresses and swelling in nuclear power plant components exposed to irradiation directly from the observed or computed defect and dislocation microstructure is a fundamental problem of fusion power plant design that has so far eluded a practical solution. We develop a model, free from parameters not accessible to direct evaluation or observation, that is able to provide estimates for irradiation-induced stresses and strains on a macroscopic scale, using information about the distribution of radiation defects produced by high-energy neutrons in the microstructure of materials. The model exploits the fact that elasticity equations involve no characteristic spatial scale, and hence admit a mathematical treatment that is an extension to that developed for the evaluation of elastic fields of defects on the nanoscale. In the analysis given below we use, as input, the radiation defect structure data derived from ab initio density functional calculations and large-scale molecular dynamics simulations of high-energy collision cascades. We show that strains, stresses and swelling can be evaluated using either integral equations, where the source function is given by the density of relaxation volumes of defects, or they can be computed from heterogeneous partial differential equations for the components of the stress tensor, where the density of body forces is proportional to the gradient of the density of relaxation volumes of defects. We perform a case study where strains and stresses are evaluated analytically and exactly, and develop a general finite element method implementation of the method, applicable to a broad range of predictive simulations of strains and stresses induced by irradiation in materials and components of any geometry in fission or fusion nuclear power plants. ; Peer reviewed

Topics
  • density
  • impedance spectroscopy
  • simulation
  • molecular dynamics
  • dislocation
  • elasticity
  • tungsten
  • defect structure