Extraction of tensile properties of metallic alloys by small punch test: benchmarking inverse finite element method versus empirical correlations

IF 2 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Alexander Bakaev , Dmitry Terentyev , Chih-Cheng Chang , Thomas Melkior
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Abstract

The miniaturized specimens of three metallic alloys (bainitic reactor pressure vessel steel, ferritic-martensitic steel Eurofer97 and fcc CuCrZr alloy) important for nuclear and fusion applications are subjected to the small punch tests (SPTs) at room and elevated (300°C) temperatures. The baseline plasticity metric, such as yield stress, is extracted from the SPT results by means of various empirical and FEM-assisted correlations and inverse finite element method (IFEM) simulations. Further strain hardening data (up to 10 % plastic strain) is also extracted from the SPT results by the IFEM. Later on, the accuracy of the derived yield stress and strain hardening behavior is compared with the reference results of the uniaxial tensile tests.
For both studied temperatures the IFEM calculations were proven to show the best overall accuracy for the extraction of the yield stress for all the studied materials. As a simplified alternative, the FEM-assisted single-value empirical correlation based on the method from the European EN standard can be recommended for the extraction of the yield stress from RPV steels. The extraction of strain hardening behavior up to 5 % plastic strain from SPTs at both test temperatures was found to be consistently feasible only for softer alloys such as CuCrZr.
通过小冲孔试验提取金属合金的拉伸性能:基准逆有限元法与经验相关性
三种金属合金(贝氏体反应堆压力容器钢,铁素体-马氏体钢Eurofer97和fcc CuCrZr合金)的小型化试样在室温和高温(300°C)下进行了小冲压试验(SPTs)。基线塑性指标,如屈服应力,是通过各种经验和有限元辅助相关性和逆有限元法(IFEM)模拟从SPT结果中提取出来的。IFEM还从SPT结果中提取了进一步的应变硬化数据(高达10%的塑性应变)。随后,将导出的屈服应力和应变硬化行为的准确性与单轴拉伸试验的参考结果进行了比较。对于这两种研究温度,IFEM计算被证明在提取所有研究材料的屈服应力方面具有最佳的总体准确性。作为一种简化的替代方法,可以推荐基于欧洲EN标准方法的有限元辅助单值经验关联法提取RPV钢的屈服应力。在两种测试温度下,从spt中提取高达5%塑性应变的应变硬化行为被发现只适用于较软的合金,如CuCrZr。
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来源期刊
Fusion Engineering and Design
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.
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