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)

  • 2015Gamma irradiation resistance of an early age slag-​blended cement matrix for nuclear waste encapsulation33citations
  • 2010Spectroelectrochemical Study of Stainless Steel Corrosion in NaCl-KCl Melt11citations
  • 2010Corrosion of Stainless Steel in NaCl-KCl Based Melts14citations

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Chart of shared publication
Bernal, Susan A.
1 / 42 shared
Provis, John L.
1 / 52 shared
Mobasher, Neda
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Sharrad, Clint A.
1 / 9 shared
May, Iain
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Abramov, Alexander V.
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Griffiths, Trevor R.
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Rebrin, Oleg I.
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Volkovich, Vladimir A.
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Polovov, Ilya B.
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Denisov, Eugeniy
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Chart of publication period
2015
2010

Co-Authors (by relevance)

  • Bernal, Susan A.
  • Provis, John L.
  • Mobasher, Neda
  • Sharrad, Clint A.
  • May, Iain
  • Abramov, Alexander V.
  • Griffiths, Trevor R.
  • Rebrin, Oleg I.
  • Volkovich, Vladimir A.
  • Polovov, Ilya B.
  • Denisov, Eugeniy
OrganizationsLocationPeople

article

Gamma irradiation resistance of an early age slag-​blended cement matrix for nuclear waste encapsulation

  • Bernal, Susan A.
  • Provis, John L.
  • Mobasher, Neda
  • Sharrad, Clint A.
  • Kinoshita, Hajime
Abstract

Irradiation is one of the characteristic conditions that nuclear wasteforms must withstand to assure integrity during their service life. This study investigates gamma irradiation resistance of an earlyage slag cement-based grout, which is of interest for the nuclear industry as it is internationally used for encapsulation of low and intermediate level radioactive wastes. The slag cement-based grout withstands a gamma irradiation dose of 4.77 MGy over 256 h without reduction in its compressive strength; however, some cracking of irradiated samples was identified. The high strength retention is associated with the fact that the main hydration product forming in this binder, a calcium aluminum silicate hydrate (C–A–S–H) type gel, remains unmodified upon irradiation. Comparison with a heat-treated sample was carried out to identify potential effects of the temperature rise during irradiation exposure. The results suggested that formation of cracks is a combined effect of radiolysis and heating upon irradiation exposure.

Topics
  • impedance spectroscopy
  • aluminium
  • crack
  • strength
  • cement
  • forming
  • Calcium