Irradiation-assisted stress corrosion cracking of austenitic stainless steels: Recent progress and new approaches
Creators
- 1. Argonne National Lab., IL (United States). Energy Technology Div.
Description
Irradiation-assisted stress corrosion cracking (IASCC) of several types of BWR field components fabricated from solution-annealed austenitic stainless steels (SSs), including a core internal weld, were investigated by means of slow-strain-rate test (SSRT), scanning electron microscopy (SEM), Auger electron spectroscopy (AES), and field-emission-gun advanced analytical electron microscopy (FEG-AAEM). Based on the results of the tests and analyses, separate effects of neutron fluence, tensile properties, alloying elements and major impurities identified in the American Society for Testing and Materials (ASTM) specifications, minor impurities, water chemistry, and fabrication-related variables were determined. The results indicate strongly that minor impurities not specified by the ASTM-specifications play important roles, probably through a complex synergism with grain-boundary Cr depletion. These impurities, typically associated with steelmaking and component fabrication processes, are very low or negligible in solubility in steels and are the same impurities that have been known to promote intergranular SCC significantly when they are present in water as ions or soluble compounds. It seems obvious that IASCC is a complex integral problem which involves many variables that are influenced strongly by not only irradiation conditions, water chemistry, and stress but also iron and steelmaking processes, fabrication of the component, and joining and welding. Therefore, for high-stress components in particular, it would be difficult to mitigate IASCC problems at high fluence based on the consideration of water chemistry alone, and other considerations based on material composition and fabrication procedure would be necessary as well
Availability note (English)
MF available from INIS under the Report Number; Also available from OSTI as DE97000362; NTIS; US Govt. Printing Office Dep.Files
28012171.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 23 p.
- Report number
- ANL--ET/CP-88142
Conference
- Title
- advanced materials and technology for the 21st century.
- Acronym
- Fall annual meeting of the Japan Institute of Metals
- Dates
- 13-15 Dec 1995.
- Place
- Honolulu, HI (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 28012171
- Subject category
- S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; CHROMIUM; CRACK PROPAGATION; DATA; INTERGRANULAR CORROSION; METALLURGICAL EFFECTS; MITIGATION; PHYSICAL RADIATION EFFECTS; REACTOR MATERIALS; STAINLESS STEEL-304; STAINLESS STEEL-316; STAINLESS STEEL-348
- Descriptors DEC
- ALLOYS; AUSTENITIC STEELS; CARBON ADDITIONS; CHEMICAL REACTIONS; CHROMIUM ALLOYS; CHROMIUM STEELS; CHROMIUM-MOLYBDENUM STEELS; CHROMIUM-NICKEL STEELS; CHROMIUM-NICKEL-MOLYBDENUM STEELS; COBALT ADDITIONS; CORROSION; CORROSION RESISTANT ALLOYS; ELEMENTS; ENRICHED URANIUM REACTORS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; INFORMATION; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS; METALS; MOLYBDENUM ALLOYS; NICKEL ALLOYS; NIOBIUM ADDITIONS; POWER REACTORS; RADIATION EFFECTS; REACTORS; STAINLESS STEELS; STEEL-CR17NI12MO3; STEEL-CR18NI11NBCO; STEEL-CR19NI10; STEELS; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; TRANSITION ELEMENTS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- Contract W-31109-ENG-38
- Funding organization
- Nuclear Regulatory Commission, Washington, DC (United States).
- Secondary number(s)
- CONF-951202--3.