The speciation of niobium in the oxide layer of an irradiated Low-Tin ZIRLO nuclear material

J. Hawes, P. Warnicke, P. Burr, D. Ferreira Sanchez, D. Grolimund, J. Partezana, Y. L. Chiu, S. Abolhassani*

*Corresponding author for this work

Research output: Contribution to journalArticlepeer-review

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Abstract

In this study the oxidation state of niobium, within the oxide layer of a low-tin ZIRLO1 irradiated in a nuclear reactor, is examined using synchrotron. The unique set up allows simultaneous acquisition of X-ray florescence (XRF) and X-ray diffraction (XRD) maps. A gradual oxidation and evolution of niobium is observed and quantified which is then compared with the information on the distribution of oxide phases revealed by XRD. The results are discussed with the aim to better understand the hydrogen uptake mechanism for this material, particularly the cause of the increased resistance to hydrogen uptake seen in niobium containing alloys.

Original languageEnglish
Article number109630
Number of pages12
JournalCorrosion Science
Volume190
Early online date16 Jun 2021
DOIs
Publication statusPublished - Sept 2021

Bibliographical note

Funding Information:
The authors wish to acknowledge swissnuclear for the support of the HyUp research project, from financial and technical point of view. The sample has been provided by Westinghouse and within the frame of the MUZIC-3 working group activities. The authors acknowledge the sample preparation by Dr. Pia Tijeland and her team. Prof. Adrien Couet is acknowledged for the supply of NbO (2+) spectra. Mr Go Sajiki and Prof. Kiyotaka Asakura are thanked for the supply of Nb2O3 (3+) spectra. Sensitivity analysis of the quality of fit of the XANES results was performed with the assistance of resources and services from the Australian National Computational Infrastructure, MASSIVE, the Pawsey Supercomputing Centre and by Intersect Australia Ltd.

Publisher Copyright:
© 2021 Elsevier Ltd

Keywords

  • Hydrogen uptake
  • Irradiated
  • Niobium
  • XANES
  • XRD
  • Zirconium based fuel cladding

ASJC Scopus subject areas

  • General Chemistry
  • General Chemical Engineering
  • General Materials Science

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