Sökning: "atom probe tomography"

Visar resultat 16 - 20 av 45 avhandlingar innehållade orden atom probe tomography.

  1. 16. Radiation Induced Precipitation in Reactor Pressure Vessel Steel Welds

    Författare :Kristina Lindgren; Chalmers tekniska högskola; []
    Nyckelord :TEKNIK OCH TEKNOLOGIER; ENGINEERING AND TECHNOLOGY; NATURVETENSKAP; NATURAL SCIENCES; precipitation; irradiation damage; low alloy steel; reactor pressure vessel; atom probe tomography;

    Sammanfattning : Radiation induced clustering and precipitation affect the mechanical properties of the reactor pressure vessel (RPV) of a nuclear power plant, i.e. the material becomes embritteled. The combination of low Cu (0. LÄS MER

  3. 17. Development of a new generation of 12% Cr steels: Z-phase strengthened steels

    Författare :Masoud Rashidi; Chalmers tekniska högskola; []
    Nyckelord :TEKNIK OCH TEKNOLOGIER; ENGINEERING AND TECHNOLOGY; atom probe tomography; Z-phase; 9-12% Cr steels; martensitic steels; transmission electron microscopy; precipitation hardening; creep;

    Sammanfattning : Fossil-fuel fired steam power plants provide more than 60% of the electricity generated worldwide, and account for about one third of the global CO2 emissions. The thermal efficiency of the steam power plants is limited by the maximum allowed steam temperature and pressure, which in turn are determined by the long-term corrosion and creep resistance of economically viable materials. LÄS MER

  4. 18. Effects of Irradiation and Thermal Ageing on the Nanoscale Chemistry of Steel Welds

    Författare :Kristina Lindgren; Chalmers tekniska högskola; []
    Nyckelord :NATURVETENSKAP; NATURAL SCIENCES; TEKNIK OCH TEKNOLOGIER; ENGINEERING AND TECHNOLOGY; spinodal decomposition; thermal ageing; low alloy steel; reactor pressure vessel; irradiation damage; atom probe tomography; core barrel; clustering;

    Sammanfattning : Structural materials of nuclear power plants degrade during operation due to thermal ageing and irradiation from the reactor core. Effects on the materials are an increase in hardness and tensile strength, and a decrease in ductility and fracture toughness, i. e. embrittlement. LÄS MER

  5. 19. 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

  7. 20. Cold spray Cr-coated Optimized ZIRLO claddings: an option for accident tolerant fuels

    Författare :Andrea Fazi; Chalmers tekniska högskola; []
    Nyckelord :TEKNIK OCH TEKNOLOGIER; ENGINEERING AND TECHNOLOGY; TEKNIK OCH TEKNOLOGIER; ENGINEERING AND TECHNOLOGY; TEKNIK OCH TEKNOLOGIER; ENGINEERING AND TECHNOLOGY; Cr coating; atom probe tomography; cold spray; accident tolerant fuel;

    Sammanfattning : Accident tolerant fuel development has started with the aim of providing nuclear fuels able to endure severe accident conditions. Research in this field has also sparked a wave of material renewal in the nuclear industry that had being delayed for the last few decades. LÄS MER