Published December 1996 | Version v1
Journal article

Irradiation-assisted stress corrosion cracking of austenitic stainless steels: recent progress and new approaches

  • 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. (orig.)

Additional details

Publishing Information

Journal Title
Journal of Nuclear Materials
Journal Volume
239
Journal Page Range
p. 61-79.
ISSN
0022-3115
CODEN
JNUMAM

Conference

Title
Advanced materials and technology for the 21st century.
Acronym
117. Fall annual meeting of the Japan Institute of Metals (JIM)
Dates
13-15 Dec 1995.
Place
Honolulu, HI (United States).

INIS

Country of Publication
Netherlands
Country of Input or Organization
Netherlands
INIS RN
28020817
Subject category
S36: MATERIALS SCIENCE; S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
AUGER ELECTRON SPECTROSCOPY; BWR TYPE REACTORS; CRACK PROPAGATION; FISSION NEUTRONS; GRAIN BOUNDARIES; HYDROGEN EMBRITTLEMENT; IMPURITIES; MANUFACTURING; NEUTRON FLUENCE; RADIATION HARDENING; REACTOR COMPONENTS; SCANNING ELECTRON MICROSCOPY; SEGREGATION; STAINLESS STEEL-304; STAINLESS STEEL-348; STRAIN RATE; STRESS CORROSION; TRANSMISSION ELECTRON MICROSCOPY; WATER CHEMISTRY; WELDING; YIELD STRENGTH
Descriptors DEC
ALLOYS; AUSTENITIC STEELS; BARYONS; CARBON ADDITIONS; CHEMICAL REACTIONS; CHEMISTRY; CHROMIUM ALLOYS; CHROMIUM-NICKEL STEELS; COBALT ADDITIONS; CORROSION; CORROSION RESISTANT ALLOYS; CRYSTAL STRUCTURE; ELECTRON MICROSCOPY; ELECTRON SPECTROSCOPY; ELEMENTARY PARTICLES; EMBRITTLEMENT; ENRICHED URANIUM REACTORS; FABRICATION; FERMIONS; HADRONS; HARDENING; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; JOINING; MATERIALS; MECHANICAL PROPERTIES; MICROSCOPY; MICROSTRUCTURE; NEUTRONS; NICKEL ALLOYS; NIOBIUM ADDITIONS; NUCLEONS; PHYSICAL RADIATION EFFECTS; POWER REACTORS; RADIATION EFFECTS; REACTORS; SPECTROSCOPY; STAINLESS STEELS; STEEL-CR18NI11NBCO; STEEL-CR19NI10; STEELS; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS