Published April 2010
| Version v1
Journal article
Atomistic simulations of stress corrosion cracking
Description
Stress corrosion cracking (SCC) of stainless steels and nickel alloys in pressurised water reactors (PWR) has been studied for many years but the mechanism at atomic scale is still under debate. The purpose of this paper is to use atomistic calculations, molecular statics (MS) to describe the sequence of phenomena occurring at the crack tip of an SCC fracture. MS simulations with EAM potentials have been carried out on Ni bicrystals containing hydrogen. The calculations show that compression force applied on the crack lips with H at the GB causes brittle rupture. A theoretical model of SCC cracking has been proposed which fits particularly SCC of irradiated stainless steels (IASCC).
Availability note (English)
Available from http://dx.doi.org/10.1016/j.corsci.2009.12.024Additional details
Identifiers
- DOI
- 10.1016/j.corsci.2009.12.024;
- PII
- S0010-938X(09)00639-8;
Publishing Information
- Journal Title
- Corrosion Science
- Journal Volume
- 52
- Journal Issue
- 4
- Journal Page Range
- p. 1247-1257
- ISSN
- 0010-938X
- CODEN
- CRRSAA
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 41068719
- Subject category
- S36: MATERIALS SCIENCE;
- Descriptors DEI
- BICRYSTALS; COMPRESSION; CRACKS; FRACTURES; HYDROGEN; NICKEL; NICKEL ALLOYS; PWR TYPE REACTORS; RUPTURES; SIMULATION; STAINLESS STEELS; STRESS CORROSION
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; CHEMICAL REACTIONS; CORROSION; CRYSTALS; ELEMENTS; ENRICHED URANIUM REACTORS; FAILURES; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; METALS; NONMETALS; POLYCRYSTALS; POWER REACTORS; REACTORS; STEELS; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; TRANSITION ELEMENTS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Copyright
- Copyright (c) 2010 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.