Correlation of intergranular stress corrosion cracking susceptibility with mechanical response of irradiated, thermally sensitized type 304 stainless steel
- Central Research Inst. of Electric Power Industry, Komae, Tokyo (Japan). Komae Research Lab.
- Japan Atomic Energy Research Inst., Ibaraki (Japan). Oarai Research Establishment
Intergranular stress corrosion cracking (IGSCC) susceptibility of irradiated, thermally sensitized type 304 (UNS S30400) stainless steels (SS) was studied as a function of neutron fluence and correlated with mechanical responses of the materials. Neutron irradiation was carried out to neutron fluences up to 5.4 {times} 10{sup 23} n/m{sup 2} (E > 1 MeV) at 290 C and to 1.1 {times} 10{sup 24} n/m{sup 2} (E > 1 MeV) at 340 C in the Japan Material Test Reactor. Irradiated specimens were examined by slow strain rate tensile testing (SSRT) in 290 C pure water of 0.2 ppm dissolved oxygen (DO) concentration, by SSRT at 290 C in argon gas, and by microhardness measurements. IGSCC susceptibility increased with neutron fluences up to 1.1 {times} 10{sup 24} n/m{sup 2} regardless of irradiation temperatures. The 0.2% proof stress (PS) and the grain-boundary (GB{sub HV}) and grain-center microhardness (GC{sub HV}) increased. The uniform elongation (UE) decreased with neutron fluences up to 5.4 {times} 10{sup 23} n/m{sup 2} fluence was achieved at 340 C. Excellent correlation was identified between IGSCC susceptibility and microhardness increments at the grain boundary relative to the grain center. Incremental grain-boundary hardening presumably may be a major factor affecting IGSCC.
- Sponsoring Organization:
- USDOE
- OSTI ID:
- 543527
- Journal Information:
- Corrosion, Journal Name: Corrosion Journal Issue: 10 Vol. 53; ISSN 0010-9312; ISSN CORRAK
- Country of Publication:
- United States
- Language:
- English
Similar Records
Effect of neutron irradiation on intergranular stress corrosion cracking susceptibility of thermally-sensitized type 304 stainless steels
Radiation hardening and radiation-induced chromium depletion effects on intergranular stress corrosion cracking in austenitic stainless steels. [Neutron radiation]
Stress corrosion cracking of irradiated stainless steels in simulated PWR primary water
Book
·
Tue Oct 01 00:00:00 EDT 1996
·
OSTI ID:367720
Radiation hardening and radiation-induced chromium depletion effects on intergranular stress corrosion cracking in austenitic stainless steels. [Neutron radiation]
Journal Article
·
Wed Nov 30 23:00:00 EST 1994
· Corrosion (Houston); (United States)
·
OSTI ID:6656566
Stress corrosion cracking of irradiated stainless steels in simulated PWR primary water
Book
·
Sun Sep 01 00:00:00 EDT 1996
·
OSTI ID:277812