Analysis of stacking fault energy in stainless steels
Description
Current knowledge highlights the radiation induced segregation and the radiation hardening as the two main effects on irradiation assisted stress corrosion cracking (IASCC). Stacking fault energy is considered as a key parameter of materials influencing IASCC in nuclear light water reactor (LWR), because it plays an important role in every process of plastic deformation, work hardening and creep behaviour. The study of the impact of SFE variations on the plastic deformation and SCC behaviour of irradiated and unirradiated austenitic steels will contribute to the understanding of IASCC mechanism. The objective of this work, as a task within the FP6-European Project PERFECT, is to investigate the influence of the SFE on IASCC susceptibility of stainless steels, to correlation n-irradiation induced defect production, accumulation and mechanical deformation behaviour with SFE by using the state of the art experimental tools such as transmission electron microscope (TEM), positron annihilation spectroscopy (PAS), slow strain rate tests (SSRT) in simulated LWR conditions
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Additional details
Identifiers
Publishing Information
- Publisher
- Belgian Nuclear Research Center SCK-CEN
- Imprint Place
- Mol (Belgium)
- Imprint Title
- Scientific Report 2006
- Imprint Pagination
- 146 p.
- Journal Page Range
- p. 21-22
- Report number
- INIS-BE--0011
INIS
- Country of Publication
- Belgium
- Country of Input or Organization
- Belgium
- INIS RN
- 38105151
- Subject category
- S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Progress Report
- Descriptors DEI
- AUSTENITIC STEELS; BELGIUM; MATERIALS TESTING; PROGRESS REPORT; STRESS CORROSION; THERMONUCLEAR REACTORS
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; CHEMICAL REACTIONS; CORROSION; DEVELOPED COUNTRIES; DOCUMENT TYPES; EUROPE; IRON ALLOYS; IRON BASE ALLOYS; STEELS; TESTING; TRANSITION ELEMENT ALLOYS; WESTERN EUROPE
Optional Information
- Notes
- The abstract is a contribution to the 2006 Scientific Report of the Belgian Nuclear Research Centre SCK-CEN