Journal Published Online: 26 August 2016
Volume 5, Issue 1

Effect of Heat Treatment and Surface Condition on Inter-Granular Corrosion of Alloy 800



The alloy 800 is being used for steam generator tubings for pressurized heavy-water reactors (PHWRs). This material is susceptible to degradation because of severe operating conditions, like high temperature, stress, and corrosive environment. These degradation mechanisms include primary water stress corrosion cracking (PWSCC), secondary side or outer diameter stress corrosion cracking (ODSCC), inter-granular corrosion (IGC), fretting, wear, denting, high cycle fatigue, corrosion fatigue, etc. The present study was conducted to analyze the effect of solution annealing temperatures, sensitization treatments, and surface conditions on the corrosion rate. The alloy 800 tubular samples were investigated by means of a conventional corrosion test (according to ASTM G28-02) and an electrochemical potentiokinetic reactivation (EPR) test. Susceptibility to inter-granular corrosion under various experimental parameters was examined by using both the test methods and the results are compared. The observed trends in corrosion rate obtained by using conventional method and EPR test were found to be similar. These results were used to obtain most optimum heat-treatment parameters and surface condition, which will yield best corrosion resistance.

Author Information

Nayak, I.
Nuclear Fuel Complex, Hyderabad, IN
Rao, S.
Nuclear Fuel Complex, Hyderabad, IN
Kapoor, K.
Nuclear Fuel Complex, Hyderabad, IN
Pages: 14
Price: $25.00
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Stock #: MPC20160003
ISSN: 2165-3992
DOI: 10.1520/MPC20160003