High-temperature nanoindentation creep studies on castable and sintered nanostructured low-activation ferritic-martensitic alloys

IF 2.8 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY

Journal of Nuclear Materials Pub Date : 2025-04-02 DOI:10.1016/j.jnucmat.2025.155804

A. Sharma , M. Ouyang , E.D. Hintsala , D. Stauffer , W. Zhong , Y. Yang , J.R. Trelewicz , L.L. Snead , D.J. Sprouster

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Abstract

In this article, we present the creep characteristics of two reduced activation ferritic-martensitic steels of identical starting compositions formed by different fabrication routes: a nanostructured ferritic alloy commonly referred to as a castable nanostructured alloy (CNA) and a sintered nanostructured alloy (SNA) variant. Through a series of nanoindentation experiments spanning a temperature range of 25 °C to 650 °C, with a maximum load of 100 mN, we find creep behaviors in the cast and sintered materials to be remarkably similar. The creep stress exponent (

n

) for CNA and SNA were found to be in the range of 8–35 and the activation volume was ∼14–42

b^{3}

, underscoring a dominance of dislocation-mediated mechanisms in both alloys. Notably, we observed a decline in the creep stress exponent with increasing temperature, attributable to the heightened influence of thermally activated dislocations. This phenomenon suggests a potential transition in the deformation mechanism towards a thermally activated dislocation climb process, significantly impacting the observed creep behavior.

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可浇注和烧结纳米结构低活化铁素体-马氏体合金的高温纳米压痕蠕变研究

在这篇文章中，我们展示了两种由不同制造工艺形成的具有相同起始成分的还原活化铁素体-马氏体钢的蠕变特性：一种是纳米结构铁素体合金，通常被称为可浇注纳米结构合金（CNA），另一种是烧结纳米结构合金（SNA）变体。通过一系列温度范围为25°C至650°C，最大载荷为100 mN的纳米压痕实验，我们发现铸造材料和烧结材料的蠕变行为非常相似。研究发现，CNA和SNA的蠕变应力指数(n)在8-35之间，激活体积为~ 14-42b3，这表明这两种合金中位错介导的机制占主导地位。值得注意的是，我们观察到蠕变应力指数随温度升高而下降，这是由于热激活位错的影响加剧。这一现象表明变形机制可能向热激活的位错爬升过程转变，显著影响了观察到的蠕变行为。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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来源期刊

Journal of Nuclear Materials 工程技术-材料科学：综合

CiteScore

5.70

自引率

25.80%

发文量

601

审稿时长

63 days

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.