Neutron Irradiation Induced Changes in Percent Intergranular Stress Corrosion Cracking of Thermally-sensitized Type 304 Stainless Steels

2013 ◽  
pp. 963-971
Author(s):  
Takeo Onchi ◽  
Koichiro Hide ◽  
Masami Mayuzumi ◽  
Taiji Hoshiya
Keyword(s):  
Stress Corrosion ◽  
Neutron Irradiation ◽  
Stress Corrosion Cracking ◽  
Stainless Steels ◽  
Corrosion Cracking ◽  
Intergranular Stress Corrosion ◽  
Induced Changes ◽  
Intergranular Stress Corrosion Cracking ◽  
Type 304

Intergranular Stress Corrosion Cracking of Austenitic Stainless Steels in Oxygenated High Temperature Water

CORROSION ◽  
1968 ◽  
Vol 24 (10) ◽  
pp. 319-325 ◽  
Author(s):  
J. S. ARMIJO
Keyword(s):  
High Temperature ◽  
Stress Corrosion ◽  
Stress Corrosion Cracking ◽  
Stainless Steels ◽  
Corrosion Cracking ◽  
304 Stainless Steel ◽  
Intergranular Stress Corrosion ◽  
Incoloy 800 ◽  
Intergranular Stress Corrosion Cracking ◽  
Type 304

Abstract A bellows arrangement for controlled high temperature, high pressure, stress corrosion tests of thick specimens has been used to study the intergranular stress corrosion cracking of Type 304 stainless steel and Incoloy 800 in oxygenated (~ 100 ppm) 550 F (288 C) water. Complete intergranular fracture of sensitized Type 304 stainless steels occurs after 10.4 ± 4.4 hours exposure at stress levels of 14,000 to 17,000 psi. Cracking of Incoloy 800 requires longer exposures at higher stress. Crevices are not necessary to initiate cracking of sensitized alloys.

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.

Sign in / Sign up

Export Citation Format

Share Document