Microstructural evolution, localized deformation and intergranular stress corrosion cracking of irradiated stainless steels

Book · Mon Dec 01 04:00:00 EST 1997

OSTI ID:548562

Bruemmer, S M; Cole, J I; Simonen, E P ^[1]

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1. Pacific Northwest National Lab., Richland, WA (United States)

Microstructural evolution and mechanical behavior of austenitic stainless steels are evaluated for neutron and heavy-ion irradiated materials. Radiation hardening in austenitic stainless steels is shown to result from the evolution of small interstitial dislocation loops during light-water-reactor (LWR) irradiation. The presence of these loops modifies deformation characteristics and prompts a significant increase in yield strength. Available data on stainless steels irradiated under LWR conditions have been analyzed and microstructural characteristics assessed for the critical fluence range (0.5 to 5 x 10{sup 21} n/cm{sup 2}) where irradiation-assisted stress corrosion cracking susceptibility is observed. Heavy-ion irradiations are used to produce similar defect microstructures enabling the investigation of hardening and deformation mechanisms. Scanning electron, atomic force and transmission electron microscopies are employed to examine tensile test strain rate and temperature effects on deformation characteristics. Dislocation loop microstructures promote inhomogeneous planar deformation within the matrix and regularly spaced steps at the surface during plastic deformation. Twinning is the dominant deformation mechanism at rapid strain rates and at low temperatures, while dislocation channeling is favored at slower strain rates and at higher temperatures. Both mechanisms produce highly localized deformation and large surface slip steps. Channeling, in particular, is capable of creating extensive dislocation pileups and high stresses at internal grain boundaries which may promote intergranular cracking.

• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: AC06-76RL01830; FG02-93ER12130
• OSTI ID: 548562
• Report Number(s): CONF-970332--
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
36 MATERIALS SCIENCE
CRACK PROPAGATION
EVALUATED DATA
INTERGRANULAR CORROSION
MECHANICAL PROPERTIES
MICROSTRUCTURE
MORPHOLOGICAL CHANGES
RADIATION EFFECTS
RADIATION HARDENING
STAINLESS STEEL-304L
STRESS CORROSION
WATER COOLED REACTORS