Sökning: "Zircaloy-2"

Visar resultat 1 - 5 av 11 avhandlingar innehållade ordet Zircaloy-2.

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

    Författare :Johan Eriksson; Chalmers tekniska högskola; []
    Nyckelord :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;

    Sammanfattning : 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. LÄS MER

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

    Författare :Johan Eriksson; Chalmers tekniska högskola; []
    Nyckelord :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;

    Sammanfattning : 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. LÄS MER

  4. 3. Microstructure Investigation of the Oxidation Process in Zircaloy-2 - The Effect of Intermetallic Particle Size

    Författare :Pia Tejland; Chalmers tekniska högskola; []
    Nyckelord :TEKNIK OCH TEKNOLOGIER; ENGINEERING AND TECHNOLOGY; Zircaloy-2; STEM; HAADF; ADF; FIB; SEM; EDX; APT;

    Sammanfattning : Zirconium alloys are widely used in nuclear reactors as fuel cladding tubes because of their low thermal neutron capture cross-section, good corrosion properties and satisfactory mechanical properties. With an improved corrosion resistance the alloys could be used for much longer times in the reactors, increasing fuel burn-up and decreasing the amount of radioactive waste. LÄS MER

  5. 4. Microstructure of Zirconium Alloys Oxidized in Steam

    Författare :Pia Tejland; Chalmers tekniska högskola; []
    Nyckelord :TEKNIK OCH TEKNOLOGIER; ENGINEERING AND TECHNOLOGY; EDX; ADF; TEM; Zircaloy-2; FIB-SEM; STEM; GD-OES; SPP; SEM; Zirconium; HAADF;

    Sammanfattning : Zirconium alloys are widely used in nuclear reactors as fuel cladding tubes because of their low thermal neutron capture cross-section, good corrosion properties and satisfactory mechanical properties. However, the main limiting factor of these materials is the oxidation behavior. LÄS MER

  7. 5. Matrix composition in Zircaloy

    Författare :Boel Wadman; Chalmers tekniska högskola; []
    Nyckelord :NATURVETENSKAP; NATURAL SCIENCES; zircaloy-2; zircaloy-4; corrosion resistance; uniform corrosion; matrix composition; thin oxide layers; atom probe analysis; annealing parameter;

    Sammanfattning : .... LÄS MER