Influence of mean stress and light water reactor environment on fatigue life and dislocation microstructures of 316L austenitic steel
- 1. Laboratory for Nuclear Materials, Nuclear Energy and Safety Department, Paul Scherrer Institute, 5232, Villigen, PSI (Switzerland)
- 2. CEITEC, Institute of Physics of Materials, CAS, Žižkova 22, 61662, Brno (Czech Republic)
- 3. Institute of Physics of Materials, CAS, Žižkova 22, 61662, Brno (Czech Republic)
Description
Influence of mean stress on fatigue life of the austenitic stainless steel 316 L in air and light water environments (boiling water reactor/hydrogen water chemistry) at 288 °C was determined with a series of tests carried out in load-control mode. Fatigue life was found to increase with application of compressive and tensile mean stress in air and light water reactor environments. Secondary hardening was regarded as the main reason for this behavior. A modified Smith-Watson-Topper (SWT) model was considered to account for mean stress and was shown to predict fatigue life accurately in air and water environments. The reduction of fatigue life in water environment, determined with the SWT curves, was about 2.5. Observations of the end-of-life dislocation arrangements by transmission electron microscopy showed that the dislocation microstructure depends essentially on plastic strain amplitude, which in turn is strongly correlated to stress amplitude and mean stress. The microstructures were found consistent with those usually observed after strain-controlled experiments. At rather low plastic strain amplitudes, corduroy structure consisting of small dislocation loops was observed. Acting as significant obstacle to dislocation motion, corduroy structure affects overall dislocation mobility therefore contributing to notable secondary cyclic hardening.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.jnucmat.2018.05.064Additional details
Identifiers
- DOI
- 10.1016/j.jnucmat.2018.05.064;
- PII
- S0022311518300655;
Publishing Information
- Journal Title
- Journal of Nuclear Materials
- Journal Volume
- 509
- Journal Page Range
- p. 15-28
- ISSN
- 0022-3115
- CODEN
- JNUMAM
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 49103194
- Subject category
- S36: MATERIALS SCIENCE;
- Descriptors DEI
- AIR; BWR TYPE REACTORS; DISLOCATIONS; MICROSTRUCTURE; STAINLESS STEEL-316; STRESSES; TRANSMISSION ELECTRON MICROSCOPY; VISIBLE RADIATION; WATER CHEMISTRY
- Descriptors DEC
- ALLOYS; AUSTENITIC STEELS; CARBON ADDITIONS; CHEMISTRY; CHROMIUM ALLOYS; CHROMIUM STEELS; CHROMIUM-MOLYBDENUM STEELS; CHROMIUM-NICKEL STEELS; CHROMIUM-NICKEL-MOLYBDENUM STEELS; CORROSION RESISTANT ALLOYS; CRYSTAL DEFECTS; CRYSTAL STRUCTURE; ELECTROMAGNETIC RADIATION; ELECTRON MICROSCOPY; ENRICHED URANIUM REACTORS; FLUIDS; GASES; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; LINE DEFECTS; MATERIALS; MICROSCOPY; MOLYBDENUM ALLOYS; NICKEL ALLOYS; POWER REACTORS; RADIATIONS; REACTORS; STAINLESS STEELS; STEEL-CR17NI12MO3; STEELS; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Copyright
- Copyright (c) 2017 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.