N. Castin , P. Klupś , M.J. Konstantinović , G. Bonny , M.I. Pascuet , M. Moody , L. Malerba
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引用次数: 0
Abstract
Atom probe tomography (APT) is a powerful microscopy technique to characterize nano-sized clusters of the alloying elements in the bulk of reactor pressure vessel (RPV) steels. These clusters are known to dominantly determine the evolution of mechanical properties under irradiation. The results are conventionally summarized as the overall number density N and the average diameter D of the solute clusters identified in the material. Here, we illustrate that these descriptors are intrinsically imprecise because they are steered by the parameters involved in the measurement and data processing, some of which are directly under the control of the operators, but some others not. Consequently, a direct comparison between data derived at different laboratories is compromised, and key trends such as the evolution with dose, are masked. This study relies on a state-of-the-art physical model for neutron irradiation in steels to make reliable estimates of the microstructure before the measurement is performed, which allows the prediction of the population of solute clusters that are not seen by APT. We mimic APT measurements from simulated microstructures, performing a detailed study of the effects of the parameters of the analysis. We show that the values of N and D reported in the scientific literature can be matched by the predictions of our theoretical model only if specific sets of parameters are used for each laboratory that issued the measurements. We also show that if, on the contrary, all studied cases are analyzed in a consistent way, the scatter of N and D values is reduced. Specifically, we find that the average diameter D is nearly a constant value with dose, independently of the material's chemical compositions, while N increases with dose, but is also influenced by other variables. The approach we developed and used proves to have added value as complement to APT experiments in reactor pressure vessel steels.
原子探针层析技术(APT)是一种功能强大的显微镜技术,可用于表征反应堆压力容器(RPV)钢体中合金元素的纳米级团簇。众所周知,这些团簇主要决定了辐照下机械性能的演变。研究结果通常总结为材料中已识别溶质团簇的总数量密度 N 和平均直径 D。在这里,我们要说明的是,这些描述符本质上是不精确的,因为它们受到测量和数据处理过程中的参数的影响,其中一些参数直接受操作人员的控制,而另一些参数则不受控制。因此,对不同实验室得出的数据进行直接比较会受到影响,而且关键趋势(如随剂量变化的趋势)也会被掩盖。本研究利用最先进的钢材中子辐照物理模型,在进行测量前对微观结构进行可靠的估计,从而预测 APT 无法看到的溶质团簇群。我们通过模拟微观结构模拟 APT 测量,对分析参数的影响进行了详细研究。我们的研究表明,只有在每个进行测量的实验室都使用特定参数集的情况下,科学文献中报告的 N 值和 D 值才能与我们理论模型的预测值相匹配。我们还表明,相反,如果以一致的方式分析所有研究案例,N 值和 D 值的散布就会减少。具体来说,我们发现平均直径 D 几乎是剂量的恒定值,与材料的化学成分无关,而 N 则随剂量增加,但也受其他变量的影响。事实证明,我们开发和使用的方法对反应堆压力容器钢的 APT 实验具有补充价值。
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.