Grain-boundary microchemistry and intergranular cracking of irradiated austenitic stainless steel

Conference · Wed Sep 01 00:00:00 EDT 1993

OSTI ID:10192375

Chung, H M; Ruther, W E; Sanecki, J E; Kassner, T F

Constant-extension-rate tensile tests and grain-boundary analysis by Auger electron spectroscopy were conducted on high- and commercial-purity (HP and CP) Type 304 stainless steel (SS) specimens from irradiated BWR components to identify mechanisms of irradiation-assisted stress corrosion cracking (IASCC). Susceptibility to intergranular fracture could not be correlated with radiation-induced segregation of impurities such as Si, P, C, or S, but a correlation was obtained with grain-boundary Cr concentration, indicating a role for Cr depletion. Grain-boundary chemistry was conducted on BWR neutron absorber tubes fabricated from two similar heats of HP Type 304 SS of virtually identical bulk chemical composition but exhibiting different susceptibility to IASCC after irradiation to {approx}2 {times} 10{sup 21} n/cm{sup 2} (E > 1 MeV). Grain-boundary concentrations of Cr, Ni, Si, P, S, and C of the cracking-resistant and -susceptible HP heats were virtually identical. However, grain boundaries of the cracking-resistant material contained less N and more B and Li. This observation indicates that, besides the deleterious effect of grain-boundary Cr depletion, synergism between grain-boundary segregation of N and B and transmutation to H and Li plays an important role in IASCC.

• Research Organization: Argonne National Lab., IL (United States)
• Sponsoring Organization: Nuclear Regulatory Commission, Washington, DC (United States)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 10192375
• Report Number(s): ANL/ET/CP-80756; CONF-930825-9; ON: DE94000466; TRN: 93:025419
• Resource Relation: Conference: 6. international symposium on environmental degradation of materials in nuclear power systems: water reactors,San Diego, CA (United States),1-5 Aug 1993; Other Information: PBD: Sep 1993
• Country of Publication: United States
• Language: English

Related Subjects

36 MATERIALS SCIENCE
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
STAINLESS STEEL-304
STRESS CORROSION
INTERGRANULAR CORROSION
RADIATION EFFECTS
BWR TYPE REACTORS
NEUTRON ABSORBERS
TUBES
CRACKS
FAST NEUTRONS
GRAIN BOUNDARIES
CHROMIUM
IMPURITIES
SEGREGATION
360106
360105
210100
CORROSION AND EROSION
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
BOILING WATER COOLED