A5065622353- High Temperature Alloys and Creep
- Hydrogen embrittlement and corrosion behaviors in metals
- Nuclear Materials and Properties
- Microstructure and Mechanical Properties of Steels
- Graphite, nuclear technology, radiation studies
- Fusion materials and technologies
- Fatigue and fracture mechanics
- Nuclear reactor physics and engineering
- Aluminum Alloy Microstructure Properties
- Nuclear and radioactivity studies
- Non-Destructive Testing Techniques
- Welding Techniques and Residual Stresses
- Fire effects on concrete materials
- Nuclear Physics and Applications
- Magnetic Properties and Applications
- Risk and Safety Analysis
- Metallurgical Processes and Thermodynamics
- Metallurgy and Material Forming
- Spacecraft and Cryogenic Technologies
- Metal and Thin Film Mechanics
- Simulation Techniques and Applications
- Wind and Air Flow Studies
- Nuclear Engineering Thermal-Hydraulics
- Metal Alloys Wear and Properties
VTT Technical Research Centre of Finland
2019-2023
Ferritic-martensitic steels such as T91 and T92 are currently considered candidate materials for structural applications in next generation nuclear power systems, including sodium-cooled fast reactors, owing to their low neutron cross-section attractive mechanical properties at elevated temperatures. However, accelerated degradation of microstructural is expected occur during exposure high temperatures extended times, necessitating additional data predict long-term service behavior. As part...
This work highlighted that a ground surface finish and the exposure to pressurised water reactor (PWR) environment result in decreased low-cycle fatigue lifetime, an enhanced crack initiation accelerated growth rate of 304 L austenitic stainless steel. A promotes short especially environment, due highly deformed underlying microstructure with high-angle grain boundaries grinding marks on surface. Martensite was observed vicinity secondary tips specimens tested simulated PWR primary side...
A substantial amount of research effort has been applied to the field environmentally assisted fatigue (EAF) due requirement account for EAF behaviour metals existing and new build nuclear power plants. We present results European project INcreasing Safety in NPPs by Covering Gaps Environmental Fatigue Assessment (INCEFA-PLUS), during which sensitivities strain range, environment, surface roughness, mean hold times, as well their interactions on life austenitic steels characterized. The...
Abstract A pressurized water reactor primary environment can have a deleterious effect on the fatigue lifetime of austenitic stainless steels. There is need to develop greater understanding behind behaviour One ways that we improve our mechanistic by carrying out striation spacing analysis. Striation counting widely used technique in failure investigations where it typically infer information crack progression, including estimation propagation rates and number applied loading cycles....
Abstract The European project INCEFA-PLUS characterises environmentally assisted fatigue in light water reactor conditions. aims at developing a new procedure to assess damage susceptibility nuclear power plant components. basis for the development of assessment is major test campaign carried out eleven different laboratories across Europe which will deliver approximately 200 tests. based on common matrix that was optimized by means Design Experiments method. initial focus effects and...
Abstract The European Project INCEFA-PLUS (INcreasing Safety in NPPs by Covering gaps Environmental Fatigue Assessment) characterizes environmentally assisted fatigue of stainless steels light water reactor environments. project includes a major test programme during which more than 200 tests have been carried out different laboratories across Europe. campaign was structured three successive phases with slightly foci. All testing programmes were optimized means the Design Experiment method....
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The ferritic-martensitic steel HT9 is a candidate material for fuel cladding and core components in advanced nuclear reactors, such as sodium-cooled fast thanks to their high temperature mechanical properties low susceptibility irradiation induced swelling phenomena. However, thermal stability elevated microstructural evolution these alloys may impact long-term behavior reliability. In this work, the effects of aging on have been investigated through complementary electron microscopy,...
Abstract Aging management of the existing fleet nuclear power plants is becoming an increasingly important topic, especially as many units are approaching their design lifetimes or entering long-term operation. As these continue to age, there increased probability for need repairs due extended exposure a harsh environment. It paramount that qualified and validated solutions readily available. A repair method postulated through cladding crack into low alloy steel plant’s reactor pressure...
INCEFA-PLUS (INcreasing Safety in NPPs byCovering gaps Environmental Fatigue Assessment) project characterized environmentally assisted fatigue of stainless steels light water reactor environments.During this more than 200 tests have been carried out different laboratories across Europe air and environment.Most were performed on a single batch 304L, an austenitic steel alloys employed NPPs.The addressed the effects strain amplitude, hold time periods, material roughness mean strain/stress...
Abstract As part of nuclear power plant ageing management, the increased probability a need repair welding must be taken into account along with increase lifetime. An essential prerequisite for successful and safe is that applied procedures have been properly validated qualified prior to their use. For instance, if no post-weld heat treatment can performed desired tempering effect has based on temper-bead technique, user needs scan among several available procedures. A decision made which...