4.7 Article

Evaluation of the high temperature oxidation of W-Cr-Zr self-passivating alloys

Journal

CORROSION SCIENCE
Volume 147, Issue -, Pages 201-211

Publisher

PERGAMON-ELSEVIER SCIENCE LTD
DOI: 10.1016/j.corsci.2018.11.022

Keywords

Future fusion power plant; Loss-of coolant accident; Self-passivating W alloy; W-Cr-Zr alloy; Oxidation resistance

Funding

  1. Euratom research and training programme 2014-2018 [633053]
  2. China Scholarship Council, National Magnetic Confinement Fusion Program [2014GB121001, 2014GB121001B]
  3. National Natural Science Foundation of China [51574101, 51474083, 51674095, 51675154]
  4. 111 project New Materials and Technology for Clean Energy [B18018]
  5. Open Foundation of Key Laboratory of Advanced Functional Materials and Devices of Anhui Province
  6. Double First Class enhancing independent innovation and social service capabilities of Hefei University of Technology [45000-411104/011]

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W-Cr-Zr systems with different compositions were oxidized in a mixed gas (Ar + 20 vol.% O-2) atmosphere at 1000 degrees C. The power law which was used to describe the oxidation behaviour, indicates that W-11.2wt.%Cr-1.7wt.%Zr has an excellent oxidation behaviour. As analysed from the ten-hour exposure, W-Cr-Zr thin film oxidation shows a self-passivating stage followed by a linear oxidation stage. Furthermore, a study on the addition of zirconium indicates that zirconia particles act as diffusion barriers for the chromium cation diffusion and another function as the nucleation sites for the formation of the initial oxide scale.

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