scholarly journals Radiation Hardening and Radiation-Induced Chromium Depletion Effects on Intergranular Stress Corrosion Cracking in Austenitic Stainless Steels

CORROSION ◽  
1994 ◽  
Vol 50 (12) ◽  
pp. 940-946 ◽  
Author(s):  
S. M. Bruemmer ◽  
E. P. Simonen
Keyword(s):  
Stress Corrosion ◽  
Stress Corrosion Cracking ◽  
Stainless Steels ◽  
Austenitic Stainless Steels ◽  
Corrosion Cracking ◽  
Radiation Hardening ◽  
Chromium Depletion ◽  
Intergranular Stress Corrosion ◽  
Radiation Induced ◽  
Intergranular Stress Corrosion Cracking

scholarly journals AEM and AES of radiation-induced segregation in proton-irradiated stainless steels

1994 ◽  
Vol 52 ◽  
pp. 962-963
Author(s):  
E. A. Kenik ◽  
R. D. Carter ◽  
D. L. Damcott ◽  
M. Atzmon ◽  
G. S. Was
Keyword(s):  
Grain Boundaries ◽  
Stress Corrosion ◽  
Stress Corrosion Cracking ◽  
Stainless Steels ◽  
Analytical Electron Microscopy ◽  
Corrosion Cracking ◽  
Intergranular Stress Corrosion ◽  
Radiation Induced ◽  
Electron Spectrometry ◽  
Intergranular Stress Corrosion Cracking

Irradiation-assisted stress corrosion cracking (IASCC) of stainless steels has been attributed in part to radiation-induced segregation (RIS) of both major alloying and impurity elements at grain boundaries. There are phenomenological similarities observed between IASCC and intergranular stress corrosion cracking (IGSCC) of thermally-sensitized stainless steels. One concern for both IGSCC and IASCC is the localized loss of corrosion resistance associated with chromium depletion at grain boundaries. In order to avoid complications related to the long-term, induced radioactivity of neutron-irradiated specimens, four type 304L alloys were irradiated to 1 dpa (displacements per atom) with 3.4 MeV protons at 400°C. Both analytical electron microscopy (AEM) in a Philips EM400T/FEG and Auger electron spectrometry (AES) in a Perkin Elmer (PHI) 660 were employed to measure composition at or near grain boundaries in unirradiated and irradiated specimens of four controlled purity alloys [ultra-high purity (UHP), UHP+S (0.03 at.%), UHP+P (0.08 at.%), and UHP+Si (0.87 at.%)]. A sufficient number of boundaries were analyzed via AEM and AES to result in the standard deviation of the mean boundary composition of less than -0.5 at.%. Further experimental details are presented elsewhere.

Investigation of Stress Corrosion Cracking Susceptibility of Fe-Ni-Cr Alloys in Nuclear Reactor Water Environments

CORROSION ◽  
1973 ◽  
Vol 29 (1) ◽  
pp. 1-12 ◽  
Author(s):  
W. L. CLARKE ◽  
G. M. GORDON
Keyword(s):  
Stress Corrosion ◽  
Stress Corrosion Cracking ◽  
Stainless Steels ◽  
Nuclear Reactor ◽  
Austenitic Stainless Steels ◽  
Corrosion Cracking ◽  
Intergranular Stress Corrosion ◽  
Aisi Type ◽  
Intergranular Stress Corrosion Cracking ◽  
Type 304

Abstract Nonstabilized 300 series stainless steels stressed over yield are susceptible to intergranular stress corrosion cracking (SCC) when exposed in the heavily sensitized condition to 288 C (550 F), high purity water containing dissolved oxygen. The effects of stress, oxygen levels, and significant metallurgical parameters on intergranular SCC of AISI Type 304 are being evaluated. Several promising intergranular SCC resistant alternate alloys have been identified through preliminary investigations, e.g., austeno-ferritic duplex and stabilized austenitic stainless steels.

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