Grain boundary chromium concentration effects on the IGSCC and IASCC of austenitic stainless steels

Technical Report · Sun Aug 01 04:00:00 EDT 1993

DOI:https://doi.org/10.2172/10109463· OSTI ID:10109463

Bruemmer, S M; Arey, B W; Charlot, L A

Comparisons are made between grain boundary composition and intergranular stress corrosion cracking (IGSCC) of 304 and 309 austenitic stainless steels in high-temperature water environments. Chromium depletion had the dominant effect on cracking resistance with the extent of IG cracking controlled by the interfacial chromium concentration. The minimum chromium concentration required to promote cracking was a function of the applied strain rate during slow-strain-rate tensile tests in 288 C air-saturated water. Depletion from bulk levels of 18 wt% to {approximately}13.5 wt% Cr at grain boundaries prompted 100% IG cracking at a strain rate of 1 {times} 10{sup {minus}6} s{sup {minus}1}, while embrittlement was observed with only a slight depletion to {approximately}17 wt% at 2 {times} 10{sup {minus}7} s{sup {minus}1}. Insights into critical interfacial compositions promoting IGSCC are discussed in reference to cracking of irradiated stainless steel nuclear reactor core components.

• Research Organization: Pacific Northwest Lab., Richland, WA (United States)
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: AC06-76RL01830
• OSTI ID: 10109463
• Report Number(s): PNL-SA--22941; CONF-930825--15; ON: DE94004268
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220200
36 MATERIALS SCIENCE
360103
360105
360106
CARBIDES
CHROMIUM
COMPONENTS AND ACCESSORIES
CORROSION AND EROSION
CRACK PROPAGATION
EMBRITTLEMENT
EXPERIMENTAL DATA
GRAIN BOUNDARIES
INTERGRANULAR CORROSION
MECHANICAL PROPERTIES
MICROSTRUCTURE
PHYSICAL RADIATION EFFECTS
PRECIPITATION
RADIATION EFFECTS
REACTOR COMPONENTS
REACTOR MATERIALS
STAINLESS STEEL-304
STAINLESS STEEL-309
STRESS CORROSION