Search Results - "Materna, Ales"
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INFLUENCE OF RADIATION DAMAGE OF REACTOR INNER COMPONENTS ON THE RESULTS OF INDENTATION TESTS
Published in Acta Polytechnica CTU proceedings (26-06-2018)“…Irradiation of inner components of the WWER reactor type made from austenitic steel 08Ch18N10T alters their material properties and may cause component…”
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Examination of Berkovich indenter tip bluntness
Published in Materials & design (05-11-2016)“…Actual shape of the indenter is very important parameter affecting the results and interpretation of nanoindentation tests. In this study, bluntness of the tip…”
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Statistical treatment of grid indentation considering the effect of the interface and the microstructural length scale
Published in Mechanics of materials (01-01-2019)“…•Grid indentation in composite materials.•Determination of individual phase properties.•Conditional probability of indentation near the interface.•Bias of…”
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Determination of the individual phase properties from the measured grid indentation data
Published in Journal of materials research (28-11-2016)“…Statistical distribution of grid indentation data measured in multiphase materials can be significantly affected by the presence of an interface between…”
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COMPARISON OF TWO TECHNIQUES FOR EVALUATING SPHERICAL INDENTATION DATA
Published in Acta Polytechnica CTU proceedings (11-06-2020)“…Flow curves of 15Kh2MFA, Sv 08Kh19N10G2B and 08Kh18N10T steels used for fabrication of WWER-440 nuclear reactor pressure vessel and core internals were…”
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On the identification of stress–strain relation by instrumented indentation with spherical indenter
Published in Materials in engineering (01-05-2012)“…► Instrumented indentation with spherical indenter. ► Identification of stress–strain relation using Tabor’s formulae. ► Limitations due to indenter shape,…”
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Identification of neutron irradiation induced strain rate sensitivity change using inverse FEM analysis of Charpy test
Published in Journal of nuclear materials (01-04-2015)“…A simple methodology how to obtain additional information about the mechanical behaviour of neutron-irradiated WWER 440 reactor pressure vessel steel was…”
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Fatigue Crack Growth in Plasma-Sprayed Refractory Materials
Published in Journal of thermal spray technology (15-01-2019)“…Fatigue crack growth in self-standing plasma-sprayed tungsten and molybdenum beams with artificially introduced notches subjected to pure bending was studied…”
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DEFORMATION OF FE3SI SINGLE-CRYSTALS UNDER NANOINDENTATION
Published in Acta Polytechnica CTU proceedings (26-06-2018)“…Knowledge of the complex deformation behavior in the anisotropic materials is one of essential issues in materials science and it is crucial for the…”
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Comparative analysis of microstructure and fracture surfaces of blade roots
Published in Materials characterization (01-10-2009)“…Samples of chromium stainless steel were loaded to investigate fatigue crack growth in roots of steam turbine blades. Images of the material microstructure and…”
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Mechanical testing of a FW panel attachment system for ITER
Published in Fusion engineering and design (01-06-2009)“…An objective of experiments and finite element simulations was to check the stiffness, the strength and the fatigue resistance of the attachment of the First…”
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Journal Article Conference Proceeding -
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