Ö. Koç , R. Thomas , B. Jenkins , C. Hofer , Z. Hegedüs , U. Lienert , R.W. Harrison , M. Preuss , T. Ungár , P. Frankel
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引用次数: 0
Abstract
Protons are increasingly used as a surrogate for neutrons to study radiation damage of engineering alloys used in the core of a nuclear reactor, enabling high fluences in comparatively short times. However, the accelerated damage rate of protons is usually compensated by an increased irradiation temperature to assist diffusion. To better understand dose rate effects on microstructure evolution during radiation damage, recrystallized Low-Sn ZIRLO and Zircaloy-2 were proton-irradiated to 0.15 dpa at 320 °C using nominal dose rates of 1.3, 2.5, and 5.2 × 10−5 dpa/s. Depth profiling using microbeam synchrotron XRD was conducted across the 30 µm deep irradiated regions for line profile analysis, enabling dislocation line density determination. We found no significant difference in dislocation density among the different dose rates for Zircaloy-2 while Low-Sn ZIRLO displayed dose rate sensitive microstructural evolution. However, Low-Sn ZIRLO exhibited a significantly lower overall dislocation density compared to Zircaloy-2 samples at all dose rates. (S)TEM analysis of the samples showed clear 〈a〉 loop alignment in Zircaloy-2, while this was less pronounced in Low-Sn ZIRLO. APT analysis conducted on Low-Sn ZIRLO specimens showed the early onset of irradiation induced nanoclusters of Nb, where the clusters were observed to be comparatively smaller in the sample exposed to high dose rate irradiation. Overall, the integration of different techniques has provided a more comprehensive understanding of the early-stage damage evolution under differing damage accumulation rates.
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.