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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in Cooperation with on an Cooperation-Score of 37%

Topics

Publications (3/3 displayed)

  • 2023Investigation of Stress Corrosion Cracking Resistance of Irradiated 12Cr Ferritic-Martensitic Stainless Steel in Supercritical Water Environment1citations
  • 2020Analysis of mechanisms inducing corrosion cracking of irradiated austenitic steels and development of a model for prediction of crack initiation13citations
  • 2019Features of Laser Welding Light Constructions from Cryogenic Austenitic Steel 316L2citations

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Chart of shared publication
Safonov, Ivan
1 / 1 shared
Margolin, Boris
2 / 2 shared
Dub, Alexey
1 / 1 shared
Kokhonov, Vasiliy
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Pokor, Cédric
1 / 4 shared
Toivonen, Aki
1 / 60 shared
Sefta, Faiza
1 / 1 shared
Pirogova, Natalia
1 / 1 shared
Kuznetsov, M.
1 / 7 shared
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2023
2020
2019

Co-Authors (by relevance)

  • Safonov, Ivan
  • Margolin, Boris
  • Dub, Alexey
  • Kokhonov, Vasiliy
  • Pokor, Cédric
  • Toivonen, Aki
  • Sefta, Faiza
  • Pirogova, Natalia
  • Kuznetsov, M.
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article

Analysis of mechanisms inducing corrosion cracking of irradiated austenitic steels and development of a model for prediction of crack initiation

  • Margolin, Boris
  • Pokor, Cédric
  • Sorokin, Alexander
  • Toivonen, Aki
  • Sefta, Faiza
  • Pirogova, Natalia
Abstract

The austenitic steels used for RPV internals of light water reactors (LWR) are considered. Mechanisms having a potential effect on irradiation assisted stress corrosion cracking (IASCC) of austenitic steels in the LWR environment have been analyzed. Based on the analysis and generalization of reference and original data on IASCC, an IASCC initiation criterion has been formulated. The nature of low-temperature creep of irradiated austenitic steels has been considered, constitutive equations have been derived. Relying on the formulated criterion of grain-boundary microcrack nucleation and the derived creep equations, an IASCC initiation model has been developed. The model allows one to predict the dependence of the threshold stress σ th IASCC on neutron dose and also to calculate the IASCC initiation time with stresses exceeding σ th IASCC .

Topics
  • grain
  • grain boundary
  • crack
  • steel
  • creep
  • stress corrosion