Assessment of the impact behavior of CLF-1 steel with Charpy V-notch testing and miniature Charpy V-notch testing

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Fusion Engineering and Design Pub Date : 2024-10-22 DOI:10.1016/j.fusengdes.2024.114692

Zhanze Shi, Zhuohui Chen, Bintao Yu, Hu Lin, Bing Bai, Xinfu He

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Abstract

China Low-activation Ferrite steel (CLF-1), as one of the structural materials developed in China for fusion reactors, is a Reduced activation Ferritic/Martensitic (RAFM) steel modeled after the traditional T91 steel (9Cr-1Mo-0.2V-0.08Nb). For fusion reactor materials, the Charpy impact testing is an important method to assess their notch sensitivity. In this study, Charpy impact tests were conducted on CLF-1 steel using Charpy V-notch specimens (CVN) and Miniature Charpy V-notch specimens (Kleinstprobe, KLST) to assess the impact behavior of CLF-1 steel, and data normalization was performed on the KLST specimen. The results show that as the specimen size of CLF-1 steel decreased, the curves of impact absorbed energy, lateral expansion, and shear fracture appearance shifted towards lower temperatures, and the impact absorbed energy significantly decreased. Both the macroscopic and microscopic characteristics of the specimens obtained from the experiments indicated that KLST specimens could achieve the same fracture characteristics as CVN specimens. Additionally, at the same experimental temperature, KLST specimens exhibited a higher proportion of ductile fracture regions.

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通过夏比 V 型缺口试验和微型夏比 V 型缺口试验评估 CLF-1 钢的冲击行为

中国低活化铁素体钢（CLF-1）是中国为聚变反应堆开发的结构材料之一，是一种以传统 T91 钢（9Cr-1Mo-0.2V-0.08Nb）为模型的低活化铁素体/马氏体（RAFM）钢。对于聚变反应堆材料而言，夏比冲击试验是评估其缺口敏感性的重要方法。本研究使用夏比 V 型缺口试样（CVN）和微型夏比 V 型缺口试样（Kleinstprobe，KLST）对 CLF-1 钢进行了夏比冲击试验，以评估 CLF-1 钢的冲击行为，并对 KLST 试样进行了数据归一化处理。结果表明，随着 CLF-1 钢试样尺寸的减小，冲击吸收能量、横向膨胀和剪切断裂外观曲线向低温方向移动，冲击吸收能量显著降低。实验所得试样的宏观和微观特征均表明，KLST 试样可获得与 CVN 试样相同的断裂特征。此外，在相同的实验温度下，KLST 试样表现出更高比例的韧性断裂区域。

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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.