A5038498607- Nuclear Materials and Properties
- Nuclear reactor physics and engineering
- Fusion materials and technologies
- High Temperature Alloys and Creep
- Nuclear Engineering Thermal-Hydraulics
- Engineering Applied Research
- Nuclear and radioactivity studies
- Magnesium Alloys: Properties and Applications
- Aluminum Alloy Microstructure Properties
- High-Temperature Coating Behaviors
- Thermodynamic and Structural Properties of Metals and Alloys
- Radioactive element chemistry and processing
- Microstructure and mechanical properties
- Mechanical Failure Analysis and Simulation
- Metallurgy and Material Forming
- Chemical Looping and Thermochemical Processes
- Aluminum Alloys Composites Properties
Korea Atomic Energy Research Institute
2014-2023
The effects of hydrogen precipitation on the mechanical properties Zircaloy–4 and Zirlo alloys were examined with uniaxial tensile tests at room temperature 400 °C accompanying microstructural changes in alloy specimens discussed. elastic moduli decreased increasing concentrations. Yield strengths both materials tended to decrease gradually. reductions yield stress seems be caused by dissipation point phenomena shown stress-strain curves. Ultimate (UTS) slightly increased low contents, then...
A hydride reorientation can deteriorate the mechanical ductility of spent fuel cladding and make it more susceptible to failure. Therefore, an evaluation under dry storage conditions their effects on are critical issues in terms regulation criteria. In this work, biaxial stress was applied Zircaloy-4 by pressurizing Ar gas. The study showed that occur at around 60 80 MPa 400 300 °C, respectively. ring compression test room temperature decreases with increase radial quantity: Fl(45)...
TSSD, TSSP, and TSSP2 of hydrogen for optimized-Zirlo (Zirlo™) alloy were measured by DSC in the range 53–457 wppm. Solvus curves TSSs are derived proposed this study. The results show that temperature gap between TSSD TSSP solvus lines Zirlo™ similar to those other zirconium alloys, but another line differs significantly. In particular, becomes closer than unlike Zircaloy-4, so ΔTTSSD-TSSP2 decreases with decreasing temperature. This implies hydride reorientation can take place more...
Zircaloy-4 has been of great interest as the core material for nuclear fuel cladding and assembly in pressurized water reactor (PWR) since it does not only have substantially low neutron absorption during power generation, but also show superior mechanical properties including high corrosion resistance radiation environment [ 1 ]. However, excessive hydrogen (H) is precipitated zirconium (Zr) hydride with form platelets Zr when H concentration exceeds terminal solid solubility (TSS), which...