[1. Garzarolli F., Riess R.: International Conference on Interaction of Non-Iron Based Materials with Water and Steam, June 1996, Piacenza, Italy.]Search in Google Scholar
[2. Göhr, H.; Impedance studies oft he oxide layer on zircaloy after previous oxidation in water vapour at 400 °C. Electrochimica Acta1993, 38, 1961-1964.]Search in Google Scholar
[3. Allen, T.R.; Corrosion of Zirconium Alloys. Comprehensive Nuclear Materials2012, 5, 49-68.10.1016/B978-0-08-056033-5.00063-X]Search in Google Scholar
[4. Hillner, E.; Long-term corrosion of Zircaloy before and after irradiation. Journal of Nuclear Materials2000, 278, 334.10.1016/S0022-3115(99)00230-5]Search in Google Scholar
[5. Bataillon, C.; Féron, D.; Marchetti. L.; E-DEN Monograph Corrosion Commissariat á l’Énergie Atomique; 2008.]Search in Google Scholar
[6. Yilmazbayhan, A.; Structure of zirconium alloy oxides formed in pure water studied with synchrotron radiation and optical microscopy: relation to corrosion rate. Journal of Nuclear Materials2004, 324, 6-22.]Search in Google Scholar
[7. Corrosion of Zirconium and its Alloys, Elsevier: Happy Valley, USA; Yau, T.; 2010.]Search in Google Scholar
[8. Oxidation of Intermetallic Precipitates in Zircaloy-4: Impact of Irradiation, Zirconium in the Nuclear Industry: 10th International Symposium, ASTM STP 1245; Pecheur, D.; et al. 1994.]Search in Google Scholar
[9. Pecheur, D.; Precipitate evolution in the Zircaloy-4 oxide layer. Journal of Nuclear Materials1992, 189, 318-332.]Search in Google Scholar
[10. Cox, B.; Some thoughts on the mechanisms of in-reactor corrosion of zirconium alloys. Journal of Nuclear Materials2005, 336, 331-368.]Search in Google Scholar
