Quantitative prediction of environmentally assisted cracking
Creators
- 1. General Electric Research and Development Center, Schenectady, NY (United States)
Description
It has long been recognized that the stress corrosion cracking (SCC) and corrosion fatigue cracking susceptibility of various alloy and environment systems is dependent upon complex interactions between stress, material, and environmental parameters. This complexity can lead to scatter in cracking responses that, in turn, leads to difficulty in predicting the life of engineering structures. F.P. Ford was the 1995 recipient of the W.R. Whitney Award sponsored by NACE International. The present work is taken from his award lecture at CORROSION/95 held in March 1995 in Orlando, Florida. His lecture focused on how these interactions may be predicted quantitatively for ductile alloys in aqueous environments with knowledge of the cracking mechanism. This capability may lead to life prediction of critical structures in, for instance, boiling-water nuclear reactors (BWR)
Additional details
Publishing Information
- Journal Title
- Corrosion (Houston)
- Journal Volume
- 52
- Journal Issue
- 5
- Journal Page Range
- p. 375-395.
- ISSN
- 0010-9312
- CODEN
- CORRAK
Conference
- Title
- National Association of Corrosion Engineers (NACE) international annual conference and corrosion show.
- Acronym
- Corrosion '95
- Dates
- 26-31 Mar 1995.
- Place
- Orlando, FL (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 27059972
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AUSTENITIC STEELS; BWR TYPE REACTORS; CORROSION RESISTANT ALLOYS; CRACK PROPAGATION; FATIGUE; FORECASTING; LOW ALLOY STEELS; PHYSICAL RADIATION EFFECTS; SERVICE LIFE; STAINLESS STEELS; STRESS CORROSION
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; CHEMICAL REACTIONS; CORROSION; ENRICHED URANIUM REACTORS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; LIFETIME; MECHANICAL PROPERTIES; POWER REACTORS; RADIATION EFFECTS; REACTORS; STEELS; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-950304--.