Y. Pushpalatha Devi , K.V. Mani Krishna , N. Keskar , J.B. Singh , R.N. Singh
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On the microstructural evolution and hydriding behavior of dilute Zr-2.5Nb-Y alloys
Zr-2.5Nb alloy is a critical pressure tube material in pressurized heavy water reactors (PHWRs), as its performance directly influences the operational life and safety of the reactor. However, the formation of hydrides in this alloy can detrimentally affect its mechanical properties. In the present study, yttrium was employed as a dilute addition to mitigate hydride embrittlement. Alloys were prepared with varying yttrium contents of 0.5 to 2 wt %. Yttrium addition resulted in the formation of fine yttria precipitates. The hot deformed microstructures of alloys with Y exhibited significant differences in morphology of the phases and prior β phase fraction when compared to reference Zr2.5Nb alloy. Dilatometry studies indicated that yttrium addition led to a reduction in the β-transus temperature of the alloy. The hydride behavior of the alloys was also examined, showing that yttrium significantly reduced hydride size to <20 μm, compared to a range of 10–150 μm in the absence of yttrium (Zr-2.5Nb). This comprehensive study of the microstructure and hydriding behavior, with the addition of yttrium to the Zr-2.5Nb alloy, suggests that yttrium may be considered for improving the alloy's performance in nuclear applications, in view of the mitigation of hydride embrittlement.
期刊介绍:
The Journal of Nuclear Materials publishes high quality papers in materials research for nuclear applications, primarily fission reactors, fusion reactors, and similar environments including radiation areas of charged particle accelerators. Both original research and critical review papers covering experimental, theoretical, and computational aspects of either fundamental or applied nature are welcome.
The breadth of the field is such that a wide range of processes and properties in the field of materials science and engineering is of interest to the readership, spanning atom-scale processes, microstructures, thermodynamics, mechanical properties, physical properties, and corrosion, for example.
Topics covered by JNM
Fission reactor materials, including fuels, cladding, core structures, pressure vessels, coolant interactions with materials, moderator and control components, fission product behavior.
Materials aspects of the entire fuel cycle.
Materials aspects of the actinides and their compounds.
Performance of nuclear waste materials; materials aspects of the immobilization of wastes.
Fusion reactor materials, including first walls, blankets, insulators and magnets.
Neutron and charged particle radiation effects in materials, including defects, transmutations, microstructures, phase changes and macroscopic properties.
Interaction of plasmas, ion beams, electron beams and electromagnetic radiation with materials relevant to nuclear systems.