Effect of Steam Temperature and Pressure on the Oxidation of Potential Coating alloy FeCrAl for Supercritical Water Cooled Nuclear Reactor Application

[+] Author and Article Information
Bingjie Xiao

PHD candidate, Carleton University, 1125 Colonel By Dr, Ottawa, K1S5B6

Xiao Huang

Professor, Carleton University, 1125 Colonel By Dr, Ottawa, K1S5B6

Qi Yang

Research Officer, 1200 Montreal Road, Ottawa, K1K2E1

Prakash Patnaik

Research Officer, 1200 Montreal Road, Ottawa, K1K2E1

1Corresponding author.

ASME doi:10.1115/1.4042500 History: Received September 07, 2018; Revised January 02, 2019


MCrAl (M=Fe, Ni or Co) alloys have exceptional corrosion and oxidation resistance and can be used as both oxidation resistant structural materials and coatings. These coatings protect high temperature steels or Ni based alloys by forming a dense alumina layer on the surface and impeding further oxidation. In order to assess its potential usage as an overlay coating on components used in supercritical water cooled nuclear reactor, a Fe-23Cr-5Al alloy in a form was tested in two different super-heated steam (SHS) conditions (625?C and 800?C) and in supercritical water (SCW) (625?C and 26 MPa), for 500 hours. The corrosion behavior of samples was assessed by measuring weight change per unit surface area and examining the surface and cross section microstructure, and the phase compositions using SEM and XRD. The samples showed different oxidation behavior after exposure to three conditions. SEM and XRD results concluded that FeCrAl has the ability to form protective Al- and Cr- containing oxide under all three conditions. Based on the findings, it is concluded that the oxidation performance of Fe-23Cr-5Al is highly influenced by pressure and temperature in the range of testing conditions. SHS exposure at lower temperature led to greater weight gain while SCW resulted in weight loss. Overall its performance is better in SHS conditions compared to CoCrWC S16, but worse in the SCW condition.

National Research Council of Canada
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