Corrosion of Zirconium Alloys Used for Nuclear Fuel Cladding

By A. Motta, A. Couet, R. Comstock. 2015

448 citations recorded by the source corpus.

Subfields: Aerospace Engineering, Materials Chemistry, Metals and Alloys

View Paper: https://www.semanticscholar.org/paper/ce1f415260bd32d2161e0fe398f56954e736ad28

How researchers see this paper

The researchers whose trusted networks rank it highest, strongest advocate first. Every researcher gets a different order.

In Aerospace Engineering

1. Michael R. Tonks
2. M. Steinbrueck
3. Long-qing Chen
4. Brian Wirth
5. H. Seifert
6. Giovanni Pastore
7. M. Stueber
8. A. Motta

In Materials Chemistry

1. Michael R. Tonks
2. Mark R. Daymond
3. M. Steinbrueck
4. Long-qing Chen
5. Laurent Capolungo
6. Brian Wirth
7. H. Seifert
8. Giovanni Pastore

Citations in the corpus

• Protective coatings on zirconium-based alloys as accident-tolerant fuel (ATF) claddings (2017, background): “Zr-based alloy claddings, such as ZIRLOTM from Westinghouse, M5® from AREVA, and E365 for Russian reactors, has been developed, which exhibit enhanced corrosion resistance under normal conditions compared to the classical alloys Zircaloy-2 and Zircaloy-4 (Gilbon et al., 2000; Motta et al., 2015).”
• Hydrogen in zirconium alloys: A review (2019, background): “The hydrogen source of greatest concern is hydrogen pickup by the zirconium alloy cladding during the corrosion reaction, equation (1) [5,23,24].”