Corrosion and stress corrosion cracking in supercritical water

By G. Was, P. Ampornrat, G. Gupta, S. Teysseyre, E. West, T. Allen, K. Sridharan, L. Tan, Yun Chen, X. Ren and 1 more. 2007

411 citations recorded by the source corpus.

Subfields: Aerospace Engineering, Biomedical Engineering, Materials Chemistry

View Paper: https://www.semanticscholar.org/paper/bc3f778ebd1a750126821bc1e81abea1f91b7b7f

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In Aerospace Engineering

1. C. Azevedo

In Materials Chemistry

1. C. Azevedo
2. W. Qu
3. R. Hui
4. Chunwen Sun
5. S. Yick

Citations in the corpus

• Selection of fuel cladding material for nuclear fission reactors (2011, background): “Increases in coolant temperature, power up-rates, extended burn-ups, and longer residence times have led to the development of new Zr alloys (see Table 6) by thermo-mechanical processing and microstructural and alloy design, but its maximum service temperature is still around 400 C, creating immense”
• Progress in corrosion resistant materials for supercritical water reactors (2009, background): “Austenitic stainless steels and Ni-base alloys have better oxidation resistance but are more susceptible to stress corrosion cracking [8].”