Development of a miniaturized ring notched bend specimen for the assessment of the fracture toughness of ODS steel fuel claddings

IF 2.8 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY

Journal of Nuclear Materials Pub Date : 2025-04-08 DOI:10.1016/j.jnucmat.2025.155810

Boualem Rais , Jérôme Garnier , Elodie Pons , Bernard Marini , Jacques Besson

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引用次数: 0

Abstract

A miniaturized Ring Notched Bend test (mRNB) was developed as a means to assess the fracture toughness of thin-walled tubes. The fracture resistance curve (J–R curve) was derived from both the load-CMOD curve and the load-LLD curve, utilizing a single specimen technique. Following the procedures proposed in the ASTM E1820 standard [1], the elastic unloading methods were employed for the load-CMOD curve. Alternatively, the normalization method was utilized to analyze the load-LLD curve when CMOD measurements was not possible. However, for the application of this methodology to the mRNB test, the standard lacks the necessary functions, including the compliance function, the geometric stress intensity function, and the plastic factor, to process the test results. In this study, the finite element analysis was used to determine the geometric functions required for crack length evaluation during the test, as well as the elastic and plastic components of the J-integral, whether derived from the load—CMOD or load—LLD curve. This methodology was applied to experimentally investigate the crack growth resistance and damage of two types of ODS (Oxide Dispersion Strengthened) steel tubes, (containing specifically 9%Cr and 14%Cr), which are considered candidate materials for fuel claddings of future fast-neutron reactors.

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用于ODS钢燃料包壳断裂韧性评估的小型环形缺口弯曲试样的研制

提出了一种小型环形缺口弯曲试验（mRNB），用于评估薄壁管的断裂韧性。采用单试件技术，分别从载荷- cmod曲线和载荷- lld曲线中得到断裂阻力曲线（J-R曲线）。按照ASTM E1820标准[1]中提出的程序，对荷载- cmod曲线采用弹性卸载方法。或者，在无法进行CMOD测量时，采用归一化方法分析负载- lld曲线。然而，为了将该方法应用于mRNB试验，该标准缺乏必要的函数，包括柔度函数、几何应力强度函数和塑性因子，以处理试验结果。在本研究中，通过有限元分析确定试验中裂纹长度评估所需的几何函数，以及j积分的弹塑性分量，无论是由荷载- cmod还是荷载- lld曲线推导。该方法应用于实验研究了两种ODS（氧化物弥散强化）钢管（含9%Cr和14%Cr）的抗裂纹扩展和损伤性，这两种钢管被认为是未来快中子反应堆燃料包壳的候选材料。

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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.