Crack initiation mechanism in non-ductile cracking of irradiated 304L stainless steels under BWR water environment
- 1. Central Research Inst. of Electric Power Industry, Komae, Tokyo (Japan)
- 2. CIEMAT, Madrid (Spain)
- 3. VTT Industrial Systems (Finland)
Description
The deformation behavior and initiation mechanisms of intergranular (IG) and transgranular (TG) cracks in irradiated 304L stainless steel were studied by slow-strain-rate tensile tests in inert gas and simulated BWR water environments, followed by fractographic and microstructural examinations. Neutron irradiation was made in test reactors to fluences of up to 6.2x1020 n/cm2 (E>1 MeV). Intergranular cracking occurred in water above a critical neutron fluence of around 1x1020 n/cm2, based on the results of the SSRT tests and SEM fractography. That critical fluence is mechanistically supported by irradiated, deformed microstructures exhibiting dislocation channeling at that fluence, while radiation-induced Cr depletion at the grain boundaries was minor. Transgranular cracking of the irradiated material occurred in water below the critical fluence, initiating in the non-uniformly strained surface region of the test bar in the later stages of plastic deformation. The initiation of TG cracking is hypothesized to be related to a high density of deformation twins. Intergranular cracking is proposed to have initiated where localized slip bands terminated at grain boundaries, while TG cracking is inferred to have initiated at deformation twin boundaries. High stress and strain concentrations at grain/twin boundaries would be the common cause of non-ductile crack initiation. (author)
Additional details
Identifiers
Publishing Information
- Journal Title
- Journal of Nuclear Science and Technology (Tokyo)
- Journal Volume
- 43
- Journal Issue
- 8
- Journal Page Range
- p. 851-865
- ISSN
- 0022-3131
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 53076802
- Subject category
- S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BWR TYPE REACTORS; CRACK PROPAGATION; DEFORMATION; DISLOCATION PINNING; FRACTOGRAPHY; GRAIN BOUNDARIES; INTERGRANULAR CORROSION; NEUTRON FLUENCE; SCANNING ELECTRON MICROSCOPY; STAINLESS STEEL-304L; STRAIN HARDENING; STRESS CORROSION; TWINNING; WATER CHEMISTRY
- Descriptors DEC
- ALLOYS; AUSTENITIC STEELS; CARBON ADDITIONS; CHEMICAL REACTIONS; CHEMISTRY; CHROMIUM ALLOYS; CHROMIUM-NICKEL STEELS; CORROSION; CORROSION RESISTANT ALLOYS; ELECTRON MICROSCOPY; ENRICHED URANIUM REACTORS; HARDENING; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; LOW CARBON-HIGH ALLOY STEELS; MATERIALS; MICROSCOPY; MICROSTRUCTURE; NICKEL ALLOYS; POWER REACTORS; REACTORS; STAINLESS STEELS; STEEL-CR19NI10-L; STEELS; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 23 refs., 16 figs., 1 tab.; This record replaces 37114000