Some thoughts on the mechanisms of in-reactor corrosion of zirconium alloys

By B. Cox. 2005

517 citations recorded by the source corpus.

Subfields: Aerospace Engineering, Materials Chemistry

View Paper: https://www.semanticscholar.org/paper/f5ff9eeef40bbc2923eba13e967f53f1febfce8f

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In Aerospace Engineering

1. A. Motta
2. A. Couet
3. R. Comstock
4. C. Azevedo

In Materials Chemistry

1. A. Motta
2. A. Couet
3. R. Comstock
4. C. Azevedo

Citations in the corpus

• Corrosion of Zirconium Alloys Used for Nuclear Fuel Cladding (2015, background): “Thus, it seems reasonable to consider that to grow micrometer-scale oxides during thermal oxidation, the effect of electron transport and electric field has to be considered (11, 115, 116).”
• Selection of fuel cladding material for nuclear fission reactors (2011, background): “The protective behaviour of the oxide layer has been associated with the texture of the oxide microstructure and the presence of interfacial tetragonal Zr3O along with monoclinic Zr2O, but the use of Zr alloys as cladding material still limits the service temperature to less than 400 C [32,57,58,68]”