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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Naji, M.
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Harrison, Robert W.

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in Cooperation with on an Cooperation-Score of 37%

Topics

Publications (13/13 displayed)

  • 2023Microstructure and radiation tolerance of molybdenum-rich glass composite nuclear waste forms5citations
  • 2023In situ TEM study of heavy-ion irradiation-induced amorphisation and electron beam-induced recrystallisation in powellite (CaMoO4)1citations
  • 2022Hydrotalcite colloid stability and interactions with uranium(VI) at neutral to alkaline pH.16citations
  • 2019Chemical effects on He bubble superlattice formation in high entropy alloys31citations
  • 2019Local chemical instabilities in 20Cr-25Ni Nb-stabilised austenitic stainless steel induced by proton irradiation9citations
  • 2019Evolution of radiation-induced lattice defects in 20/25 Nb-stabilised austenitic stainless steel during in-situ proton irradiation16citations
  • 2019Intermetallic Re phases formed in ion irradiated WRe alloy10citations
  • 2019A Transmission Electron Microscopy study of the neutron-irradiation response of Ti-based MAX phases at high temperatures36citations
  • 2018Enhanced radiation tolerance of tungsten nanoparticles to He ion irradiation17citations
  • 2017Thermal Evolution of the Proton Irradiated Structure in Tungsten–5 wt% Tantalum9citations
  • 2016Diffusion-based and creep continuum damage modelling of crack formation during high temperature oxidation of ZrN ceramics17citations
  • 2014Nuclear Applications for Ultra-High Temperature Ceramics and MAX Phases55citations
  • 2014Thermophysical characterisation of ZrCxNy ceramics fabricated via carbothermic reduction-nitridation27citations

Places of action

Chart of shared publication
Odriscoll, Brian
2 / 2 shared
Harrison, Mike
2 / 3 shared
Leay, Laura
2 / 5 shared
Shubeita, Samir De Moraes
1 / 2 shared
Taylor, Tracey
2 / 3 shared
Kaufmann, Felix E. D.
1 / 1 shared
Zagyva, Tamás
2 / 2 shared
Mir, Anamul Haq
1 / 3 shared
Haigh, Sj
1 / 63 shared
Neill, Thomas
1 / 2 shared
Sherriff, Nick
1 / 1 shared
Wilson, Hannah
1 / 1 shared
Odriozola, Laura Lopez
1 / 1 shared
Shaw, Samuel
1 / 9 shared
Natrajan, Louise
1 / 4 shared
Foster, Chris
1 / 1 shared
Bryan, Nick
1 / 1 shared
Morris, Katherine
1 / 6 shared
Rigby, Bruce
1 / 1 shared
Zou, Yi Chao
1 / 1 shared
Greaves, G.
2 / 10 shared
Donnelly, S. E.
4 / 10 shared
Zhang, Y.
1 / 149 shared
Bei, H.
1 / 14 shared
Le, H.
1 / 3 shared
Jimenez-Melero, Enrique
3 / 58 shared
Barcellini, Chiara
2 / 6 shared
Donnelly, Stephen
1 / 18 shared
Dumbill, Simon
1 / 7 shared
Dumbill, S.
1 / 3 shared
Hinks, J. A.
1 / 6 shared
Edmondson, Philip D.
1 / 8 shared
Donnelly, Stephen E.
1 / 7 shared
Tunes, Matheus Araujo
1 / 34 shared
Aradi, Emily
1 / 9 shared
Terentyev, D.
1 / 43 shared
Ipatova, I.
1 / 3 shared
Vandeperre, Luc J.
1 / 1 shared
Biglari, Farid R.
1 / 1 shared
Nikbin, Kamran
1 / 11 shared
Pettinà, Michele
1 / 1 shared
Brown, Peter
1 / 8 shared
Lee, William E.
2 / 5 shared
Rapaud, Olivier
1 / 14 shared
Maître, Alexandre
1 / 14 shared
Giorgi, Edoardo
1 / 1 shared
Lee, W. E.
1 / 11 shared
Jayaseelan, D. D.
1 / 1 shared
Ridd, O.
1 / 1 shared
Chart of publication period
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Co-Authors (by relevance)

  • Odriscoll, Brian
  • Harrison, Mike
  • Leay, Laura
  • Shubeita, Samir De Moraes
  • Taylor, Tracey
  • Kaufmann, Felix E. D.
  • Zagyva, Tamás
  • Mir, Anamul Haq
  • Haigh, Sj
  • Neill, Thomas
  • Sherriff, Nick
  • Wilson, Hannah
  • Odriozola, Laura Lopez
  • Shaw, Samuel
  • Natrajan, Louise
  • Foster, Chris
  • Bryan, Nick
  • Morris, Katherine
  • Rigby, Bruce
  • Zou, Yi Chao
  • Greaves, G.
  • Donnelly, S. E.
  • Zhang, Y.
  • Bei, H.
  • Le, H.
  • Jimenez-Melero, Enrique
  • Barcellini, Chiara
  • Donnelly, Stephen
  • Dumbill, Simon
  • Dumbill, S.
  • Hinks, J. A.
  • Edmondson, Philip D.
  • Donnelly, Stephen E.
  • Tunes, Matheus Araujo
  • Aradi, Emily
  • Terentyev, D.
  • Ipatova, I.
  • Vandeperre, Luc J.
  • Biglari, Farid R.
  • Nikbin, Kamran
  • Pettinà, Michele
  • Brown, Peter
  • Lee, William E.
  • Rapaud, Olivier
  • Maître, Alexandre
  • Giorgi, Edoardo
  • Lee, W. E.
  • Jayaseelan, D. D.
  • Ridd, O.
OrganizationsLocationPeople

article

Hydrotalcite colloid stability and interactions with uranium(VI) at neutral to alkaline pH.

  • Haigh, Sj
  • Harrison, Robert W.
  • Neill, Thomas
  • Sherriff, Nick
  • Wilson, Hannah
  • Odriozola, Laura Lopez
  • Shaw, Samuel
  • Natrajan, Louise
  • Foster, Chris
  • Bryan, Nick
  • Morris, Katherine
  • Rigby, Bruce
  • Zou, Yi Chao
Abstract

In the UK, decommissioning of legacy spent fuel storage facilities involves the retrieval of radioactive sludges that have formed as a result of corrosion of Magnox nuclear fuel. Retrieval of sludges may re-suspend a colloidal fraction of the sludge, thereby potentially enhancing the mobility of radionuclides including uranium. The colloidal properties of the layered double hydroxide (LDH) phase hydrotalcite, a key product of Magnox fuel corrosion, and it’s interactions with U(VI) are of interest. This is because colloidal hydrotalcite is a potential transport vector for U(VI) under the neutral-to-alkaline conditions characteristic of the legacy storage facilities and other nuclear decommissioning scenarios. Here, a multi-technique approach was used to investigate the colloidal stability of hydrotalcite and the U(VI) sorption mechanism(s) across pH 7 – 11.5 and with variable U(VI) surface loadings (0.01 – 1 wt%). Overall, hydrotalcite was found to form stable colloidal suspensions between pH 7 and 11.5, with some evidence for Mg2+ leaching from hydrotalcite colloids at pH ≤ 9. For systems with U present, >98% of U(VI) was removed from solution in the presence of hydrotalcite, regardless of pH and U loading, although the sorption mode was affected by both pH and U concentration. Under alkaline conditions, U(VI) surface precipitates formed on the colloidal hydrotalcite nanoparticle surface. Under more circumneutral conditions, Mg2+ leaching from hydrotalcite and more facile exchange of interlayer carbonate with the surrounding solution led to the formation of uranyl carbonate species (e.g. Mg[UO2(CO3)3]2-(aq)). Both X-ray absorption spectroscopy (XAS) and luminescence analysis confirmed these negatively charged species sorbed as both outer- and inner-sphere tertiary complexes on the hydrotalcite surface. These results demonstrate that hydrotalcite can form pseudo-colloids with U(VI) under a wide range of pH conditions and have clear implications for understanding uranium behaviour in environments where hydrotalcite and other LDHs may be present.

Topics
  • nanoparticle
  • impedance spectroscopy
  • surface
  • corrosion
  • phase
  • mobility
  • layered
  • precipitate
  • leaching
  • x-ray absorption spectroscopy
  • Uranium
  • luminescence