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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Materials Map under construction

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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Das, Suchandrima

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University of Bristol

in Cooperation with on an Cooperation-Score of 37%

Topics

Publications (6/6 displayed)

  • 2024Productive Automation of Calibration Processes for Crystal Plasticity Model Parameters via Reinforcement Learning1citations
  • 2022Modified deformation behaviour of self-ion irradiated tungsten : A combined nano-indentation, HR-EBSD and crystal plasticity study44citations
  • 2022Characterising Ion-Irradiated FeCr : Hardness, Thermal Diffusivity and Lattice Strain21citations
  • 2020Characterising Ion-Irradiated FeCr21citations
  • 2020Modified deformation behaviour of self-ion irradiated tungsten44citations
  • 2018Hardening and Strain Localisation in Helium-Ion-Implanted Tungstencitations

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Chart of shared publication
Tasdemir, Burcu
1 / 4 shared
Knowles, David M.
1 / 19 shared
Martin, Michael
1 / 3 shared
Mostafavi, Mahmoud
1 / 58 shared
Lee, Jonghwan
1 / 1 shared
Yu, Hongbing
4 / 6 shared
Mizohata, Kenichiro
4 / 99 shared
Tarleton, Edmund
2 / 16 shared
Hofmann, Felix
4 / 10 shared
Xu, Ruqing
2 / 5 shared
Song, Kay
2 / 5 shared
Phillips, Nicholas W.
2 / 2 shared
Reza, Abdallah
2 / 2 shared
Armstrong, David E. J.
2 / 7 shared
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2022
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2018

Co-Authors (by relevance)

  • Tasdemir, Burcu
  • Knowles, David M.
  • Martin, Michael
  • Mostafavi, Mahmoud
  • Lee, Jonghwan
  • Yu, Hongbing
  • Mizohata, Kenichiro
  • Tarleton, Edmund
  • Hofmann, Felix
  • Xu, Ruqing
  • Song, Kay
  • Phillips, Nicholas W.
  • Reza, Abdallah
  • Armstrong, David E. J.
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article

Characterising Ion-Irradiated FeCr

  • Xu, Ruqing
  • Yu, Hongbing
  • Das, Suchandrima
  • Song, Kay
  • Mizohata, Kenichiro
  • Phillips, Nicholas W.
  • Reza, Abdallah
  • Armstrong, David E. J.
  • Hofmann, Felix
Abstract

<p>Ion-irradiated FeCr alloys are useful for understanding and predicting neutron damage in the structural steels of future nuclear reactors. Previous studies have largely focused on the structure of irradiation induced defects, probed by transmission electron microscopy (TEM), as well as changes in mechanical properties. Across these studies, a wide range of irradiation conditions has been employed on samples with different processing histories, which complicates the analysis of the relationship between defect structures and material properties. Furthermore, key properties, such as irradiation-induced changes in thermal transport and lattice strain, are little explored.</p><p>Here we present a systematic study of Fe3Cr, Fe5Cr and Fe10Cr binary alloys implanted with 20 MeV Fe3+ ions to nominal doses of 0.01 dpa and 0.1 dpa at room temperature. Nanoindentation, transient grating spectroscopy (TGS) and X-ray micro-beam Laue diffraction were used to study the changes in hardness, thermal diffusivity and strain in the material as a function of damage and Cr content. Our results suggest that Cr leads to an increased retention of irradiation-induced defects, causing substantial changes in hardness and lattice strain. However, thermal diffusivity varies little with increasing damage and instead degrades significantly with increasing Cr content in the material. We find significant lattice strains even in samples exposed to a nominal displacement damage of 0.01 dpa. The defect density predicted from the lattice strain measurements is significantly higher than that observed in previous TEM studies, suggesting that TEM may not fully capture the irradiation-induced defect population. (C) 2020 Acta Materialia Inc. Published by Elsevier Ltd. All rights reserved.</p>

Topics
  • density
  • impedance spectroscopy
  • hardness
  • nanoindentation
  • transmission electron microscopy
  • thermogravimetry
  • defect
  • diffusivity
  • defect structure
  • structural steel