Improved approaches for small punch test to estimate the yield and ultimate tensile strength of metallic materials

IF 2.8 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY Journal of Nuclear Materials Pub Date : 2024-10-31 DOI:10.1016/j.jnucmat.2024.155490

Jiru Zhong , Mingtao Yang , Xinfu He , Kaishu Guan , Bintao Yu , Zhuangzhuang He

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Abstract

The small punch test (SPT) has been used extensively in nuclear industries to estimate mechanical properties changes of metals due to irradiation. This paper aims to propose more accurate approaches for SPT to estimate the yield and ultimate tensile strength of metals. The relationship between the SPT force and the yield and ultimate tensile strength of materials was studied by using finite element simulation data, and then three approaches were developed to determine tensile properties of materials by means of SPT. Force method and Slop method were developed to derive the ultimate tensile strength of metals from SPT curves, and Area method was proposed to determine the yield and ultimate tensile strength of metals. The accuracy of these approaches were verified by two candidate structural material for fusion reactors (CLF-1 steel and 9Cr-ODS steel) and other 10 structural materials. Area method gives more accurate evaluation on the yield strength of metals than the correlation method given in European standard on SPT. In addition, the developed approaches have advantages in estimating the tensile properties of low ductility metals.

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小冲压试验估算金属材料屈服强度和极限拉伸强度的改进方法

小冲压试验（SPT）已被广泛应用于核工业，以估算辐照导致的金属机械性能变化。本文旨在提出更精确的 SPT 方法，以估算金属的屈服强度和极限抗拉强度。利用有限元模拟数据研究了 SPT 力与材料屈服强度和极限抗拉强度之间的关系，然后开发了三种方法来通过 SPT 确定材料的拉伸性能。开发了力法和 Slop 法，从 SPT 曲线推导出金属的极限抗拉强度，并提出了面积法来确定金属的屈服强度和极限抗拉强度。聚变反应堆的两种候选结构材料（CLF-1 钢和 9Cr-ODS 钢）和其他 10 种结构材料验证了这些方法的准确性。与欧洲 SPT 标准中给出的相关方法相比，区域方法能更准确地评估金属的屈服强度。此外，所开发的方法在估算低延展性金属的拉伸性能方面也具有优势。

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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.