Published February 2013 | Version v1
Journal article

Study on corrosion behaviors of stainless steels and refractory alloys in pseudo-critical zone

  • 1. Science and Technology on Reactor Fuel and Materials Laboratory, Nuclear Power Institute of China, Chengdu (China)

Description

The general corrosion behavior of three super alloys and four austenitic stainless steels was investigated in 380℃/25 MPa deionized water. Morphology and composition of the surface oxide scale after various exposure time were analyzed through FEG-SEM and EDS. For all the tested materials, the weight gain (WG) represents no apparent regularity while the weight loss (WL) follows typical logarithmic law. HR3C showed the least WL while 347 the most, an order of magnitude difference. All the exposed samples developed relatively enact and compact dual oxide layer, with the outer layer rich in O, depleted in Cr, Ni and lack of Mo. Several alloys (316Ti, 718, 825, 800H and HR3C) displays pitting. The pits were rich in Nb and Ti, depleted in Cr and Ni, and lack of Mn and Mo, based on the alloy composition. (authors)

Additional details

Publishing Information

Journal Title
Nuclear Power Engineering
Journal Volume
34
Journal Issue
1
Journal Page Range
p. 157-161
ISSN
0258-0926

Optional Information

Notes
8 figs., 4 tabs., 13 refs.