Search for dissertations about: "Dislocation loops"

Showing result 1 - 5 of 10 swedish dissertations containing the words Dislocation loops.

2. 1. Creep modelling of particle strengthened steels

   Author : Hans Magnusson; Rolf Sandström; Göran Engberg; KTH; []
   Keywords : TEKNIK OCH TEKNOLOGIER; ENGINEERING AND TECHNOLOGY; Particle strengthening; dislocation climb; ferritic steels; dislocation evolution; creep rate modelling; Materials science; Teknisk materialvetenskap;

   Abstract : Materials to be used in thermal power plants have to resist creep deformation for time periods up to 30 years. The role of alloying elements for creep strength of 9-12% Cr steels is analysed. The creep strength in these steels relies on minor additions of alloying elements. READ MORE

4. 2. Atom probe tomography of Zircaloy-2 exposed to boiling water reactor operation

   Author : Johan Eriksson; Chalmers tekniska högskola; []
   Keywords : NATURVETENSKAP; NATURAL SCIENCES; TEKNIK OCH TEKNOLOGIER; ENGINEERING AND TECHNOLOGY; TEKNIK OCH TEKNOLOGIER; ENGINEERING AND TECHNOLOGY; TEKNIK OCH TEKNOLOGIER; ENGINEERING AND TECHNOLOGY; Nuclear fuel claddings; Zirconium alloys; Boiling water reactor; Clustering; Atom probe tomography; Radiation effects; Zircaloy-2; Dislocation loops;

   Abstract : Zirconium alloys are used as cladding tubes for the fuel in nuclear reactors. In boiling water reactors (BWRs), the alloy Zircaloy-2, which contains the alloying elements Sn, Fe, Cr, Ni, and O, is commonly used. READ MORE

5. 3. Evolution of microstructure and nanoscale chemistry of Zircaloy-2-type alloys during nuclear reactor operation

   Author : Johan Eriksson; Chalmers tekniska högskola; []
   Keywords : NATURVETENSKAP; NATURAL SCIENCES; TEKNIK OCH TEKNOLOGIER; ENGINEERING AND TECHNOLOGY; TEKNIK OCH TEKNOLOGIER; ENGINEERING AND TECHNOLOGY; TEKNIK OCH TEKNOLOGIER; ENGINEERING AND TECHNOLOGY; Zircaloy-2; Nuclear fuel cladding; Atom probe tomography; Zirconium alloys; Clustering; Dislocation loops; Radiation effects; Boiling water reactor;

   Abstract : Zirconium alloys are used as fuel cladding tubes in nuclear reactors. During reactor operation, these alloys are degraded by corrosion, hydrogen pickup (HPU), and radiation-induced growth, processes influenced by the alloying elements. READ MORE

6. 4. Electron microscopy of ion implanted silicon carbide

   Author : Per Persson; Linköpings universitet; []
   Keywords : ;

   Abstract : This thesis investigates structural defects into Silicon Carbide (SiC) in processed Al and B ion implantated samples. Ion implantation is currently the preferred way to introduce impurity atoms into the SiC crystal lattice. The structural defects found was concluded to be extrinsic dislocation loops composed of excess Si interstitials. READ MORE

7. 5. Characterization of Process-related Defects in Silicon Carbide by Electron Microscopy

   Author : Per O. Å. Persson; Pirouz Pirouz; Linköpings universitet; []
   Keywords : TEKNIK OCH TEKNOLOGIER; ENGINEERING AND TECHNOLOGY;

   Abstract : Silicon carbide (SiC) is a semiconducting material, which provides advantages compared to other available semiconducting materials. Attractive properties of SiC are the wide bandgap (2.2-3.3 eV), high electric breakdown field (3x106 Vcm-1), high thermal conductivity (5 Wcm-1 K-1) and the chemical stabi!ity. READ MORE