Application of mini-flat and cylindrical test specimens to extract hardening law and ductility of neutron irradiated Eurofer97

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Fusion Engineering and Design Pub Date : 2025-04-29 DOI:10.1016/j.fusengdes.2025.115072

Chih-Cheng Chang , Dmitry Terentyev , Alexander Bakaev , Aleksandr Zinovev , Daniele Del Serra , Patricia Verleysen , Thomas Pardoen

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Abstract

Tensile properties such as strength and ductility are essential for structural integrity assessment of critical components. In the context of nuclear applications, the flat tensile geometry as compared to the reference standard cylindrical geometry offers a number of advantages in terms of material use efficiency, ease of machining, best packing under irradiation and simplified remote handling of active samples. Accordingly, the interchangeability of data extracted from flat and cylindrical specimens is a key issue. Furthermore, this interchangeability must be demonstrated for irradiated samples. Many metallic materials show significant reduction or even a full lack of uniform elongation after neutron irradiation, with most of the strain hardening regime taking place during the post-necking stage. As the necking development depends on geometry, this raises questions on the validity of changing the test specimen geometry. Here, the interchangeability of mini-flat and cylindrical tensile samples after neutron irradiation is investigated by combining experimental and computational analysis. The investigated material is EUROFER97 steel irradiated at 300 °C in the conditions relevant for the ITER fusion reactor. Finite element (FE) simulations are performed with a Gurson-type ductile fracture model parameterized based on the experimental tensile response. The hardening law extracted from mini-flat samples and applied to predict the stress-strain response of a cylindrical sample with 90 % accuracy or better in terms of total elongation, reduction of area, and fracture strength as compared to the direct experimental data obtained with cylindrical tensile specimen geometry.

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应用微型扁平和圆柱形试样提取中子辐照后Eurofer97的硬化规律和塑性

拉伸性能，如强度和延性是至关重要的结构完整性评估的关键部件。在核应用的背景下，与参考标准圆柱形几何结构相比，平面拉伸几何结构在材料使用效率、易于加工、辐照下最佳包装和简化活性样品的远程处理方面具有许多优势。因此，从平面和圆柱形样本中提取的数据的互换性是一个关键问题。此外，这种互换性必须证明辐照样品。许多金属材料在中子辐照后伸长率明显降低，甚至完全没有均匀伸长率，大部分应变硬化发生在颈缩后阶段。由于颈缩的发展取决于几何形状，这就提出了改变试件几何形状的有效性问题。本文采用实验和计算相结合的方法，研究了中子辐照后微型扁平和圆柱形拉伸试样的互换性。所研究的材料是在与ITER聚变反应堆相关的条件下，在300°C下辐照的EUROFER97钢。采用基于试验拉伸响应参数化的gurson型韧性断裂模型进行有限元模拟。从迷你平面试样中提取的硬化规律，并应用于预测圆柱形试样的应力-应变响应，与圆柱形拉伸试样几何形状获得的直接实验数据相比，在总伸长率、面积收缩率和断裂强度方面具有90%或更高的精度。

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

Fusion Engineering and Design 工程技术-核科学技术

CiteScore

3.50

自引率

23.50%

发文量

275

审稿时长

3.8 months

期刊介绍： The journal accepts papers about experiments (both plasma and technology), theory, models, methods, and designs in areas relating to technology, engineering, and applied science aspects of magnetic and inertial fusion energy. Specific areas of interest include: MFE and IFE design studies for experiments and reactors; fusion nuclear technologies and materials, including blankets and shields; analysis of reactor plasmas; plasma heating, fuelling, and vacuum systems; drivers, targets, and special technologies for IFE, controls and diagnostics; fuel cycle analysis and tritium reprocessing and handling; operations and remote maintenance of reactors; safety, decommissioning, and waste management; economic and environmental analysis of components and systems.