Specimen size effects on tensile properties of cold worked RAFM steel

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

Fusion Engineering and Design Pub Date : 2025-04-23 DOI:10.1016/j.fusengdes.2025.115093

Pinghan Chen , Xiaochen Li , Chang Li , Mingjie Zheng , Wenyi Ding

引用次数: 0

Abstract

Changes in the mechanical properties of materials after neutron irradiation are key parameters for evaluating the properties of fusion reactor materials. Based on space, testing time span, and cost, small sized specimens are required for neutron irradiation and post-test of fusion reactor materials. In this work, the tensile properties of the small- and standard-sized specimens of 9Cr RAFM steel at different cold-work levels were tested from room temperature to 550 °C. The effects of cold-work deformation and specimen size on the tensile properties of materials were systematically analyzed, and the test data on the tensile properties of SS-J and standard-sized specimens were obtained. The effects of specimen size and cold-work deformation on the tensile properties of RAFM steel were analyzed. These research results can provide an important reference for the analysis of test data after neutron irradiation.

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试样尺寸对冷加工RAFM钢拉伸性能的影响

中子辐照后材料力学性能的变化是评价聚变反应堆材料性能的关键参数。基于空间、试验时间和成本等因素，核聚变反应堆材料的中子辐照和后试需要采用小尺寸样品。在室温至550℃范围内，对9Cr RAFM钢的小尺寸和标准尺寸试样在不同冷加工水平下的拉伸性能进行了测试。系统分析了冷加工变形和试样尺寸对材料拉伸性能的影响，获得了SS-J和标准尺寸试样拉伸性能的试验数据。分析了试样尺寸和冷加工变形对RAFM钢拉伸性能的影响。研究结果可为中子辐照后试验数据的分析提供重要参考。

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.