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 (2/2 displayed)

  • 2015Object Kinetic Monte Carlo Simulations of Radiation Damage in Neutron-Irradiated Tungsten Part-I: Neutron Flux with a PKA Spectrum Corresponding to the High-flux Isotope Reactor1citations
  • 2009Phase-field Modeling of Gas Bubbles and Thermal Conductivity Evolution in Nuclear Fuels108citations

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Chart of shared publication
Setyawana, Wahyu
1 / 1 shared
Kurtz, Richard J.
1 / 1 shared
Wirth, Brian D.
1 / 2 shared
Roche, Kenneth J.
1 / 1 shared
Valone, Steven
1 / 1 shared
Baskes, Michael I.
1 / 3 shared
Stan, Marius
1 / 1 shared
Henager, Charles H.
1 / 3 shared
Hu, Shenyang Y.
1 / 2 shared
Chart of publication period
2015
2009

Co-Authors (by relevance)

  • Setyawana, Wahyu
  • Kurtz, Richard J.
  • Wirth, Brian D.
  • Roche, Kenneth J.
  • Valone, Steven
  • Baskes, Michael I.
  • Stan, Marius
  • Henager, Charles H.
  • Hu, Shenyang Y.
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document

Object Kinetic Monte Carlo Simulations of Radiation Damage in Neutron-Irradiated Tungsten Part-I: Neutron Flux with a PKA Spectrum Corresponding to the High-flux Isotope Reactor

  • Setyawana, Wahyu
  • Heinisch, Howard L.
  • Kurtz, Richard J.
  • Wirth, Brian D.
  • Roche, Kenneth J.
Abstract

Object kinetic Monte Carlo simulations were performed to study the impact of varying dose rate and grain size up to a dose of 1.0 dpa in pure, polycrystalline tungsten, subjected to a neutron irradiation having a PKA spectrum corresponding to the High Flux Isotope Reactor. The present study models defect cluster accumulation in tungsten, but does not consider the impact of transmutation or pre-existing defects beyond the grain boundary sinks, with varying grain size. With increasing dose rate, the vacancy cluster density increases, while the number density of vacancies decreases. Accordingly, the average vacancy cluster size and the fraction of vacancies that are part of visible clusters decreases with increasing dose rate. With increasing grain size, both the number densities of vacancies and vacancy clusters decrease, while both the fraction of vacancies in visible clusters and the average vacancy cluster size increase. This is caused by the pseudo-ripening of the vacancy clusters due to the longer-lived self-interstitial clusters in larger grains. The spatial ordering of vacancy clusters along {110} planes was observed for both grain sizes and all dose rates studied. Interplanar spacing increases with grain size; however, no clear dependence on dose or dose rate was observed. The results of this study show that 1D diffusion of self-interstitial clusters, while necessary, is not sufficient to form a void lattice, and that the diffusion of vacancies is also required. A methodology is suggested for choosing the simulation box dimensions so as to represent more faithfully the effects of one-dimensional migrating self-interstitial-atom clusters.

Topics
  • density
  • impedance spectroscopy
  • cluster
  • grain
  • grain size
  • grain boundary
  • simulation
  • void
  • interstitial
  • tungsten
  • one-dimensional
  • vacancy