Nan Zhou , Chengqin Zou , Guiyang Huang , Baoqin Fu , Xunxiang Hu
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引用次数: 0
Abstract
Yttrium hydride has been perceived as an excellent neutron moderator for high-temperature nuclear reactor environments, owing to the high density of hydrogen (similar to neutron mass) and superior thermal stability. There is a growing demand for large-scale, crack-free bulk yttrium hydride for the micro-nuclear reactor applications. However, fabricating crack-free yttrium hydride with desired geometry and configuration is challenging and the relatively high neutron absorption cross section of yttrium prevents its widespread use. Zirconium microalloying offers a promising solution by mitigating cracking during hydriding and enhancing neutronic performance due to zirconium’s low neutron absorption cross section, thus broadening the application of yttrium-based materials. A fundamental understanding of atomic-scale interactions between hydrogen atoms and alloying elements is essential for optimizing the processing of yttrium-based alloys and mitigate hydrogen-induced cracking. In this study, the first-principles calculations were employed to investigate hydrogen diffusion behavior and hydrogen-induced phase transformation in pure yttrium and yttrium-zirconium alloys. The results show that an optimal concentration of zirconium enhances the diffusion coefficient of interstitial hydrogen in the bulk material. Moreover, the preferred phase transformation pathway for yttrium hydride was identified, as {0001}HCP/{111}FCC & <110>HCP/<10>FCC. These findings highlight the pivotal role of hydrogen in phase transformation process and demonstrate that low zirconium concentrations promote the phase transformation of yttrium hydride. The mechanistic insights gained will aid in the development of yttrium-based alloys for high-temperature moderators in advanced nuclear reactors.
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.