Fracture behavior and KR-curve characteristics of nuclear graphite IG11 under three-point bending tests

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

Journal of Nuclear Materials Pub Date : 2025-03-01 DOI:10.1016/j.jnucmat.2025.155724

Hengchang Liu , Jie Shen , Jing Chen , Hongniao Chen , Yuxiang Tang

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Abstract

Three-point bending tests were conducted on single edge center-notched beams to study the fracture behavior of nuclear graphite IG11. Full-field information of surface deformation of the specimens was measured by digital image correlation (DIC) technique while internal micro-cracks and damage of the specimen were monitored using acoustic emission (AE) technique. The initiation and evolution of crack and fracture process zone (FPZ) were studied and the factors affecting the behavior of K_R-curves were investigated. Based on the test results, fracture toughness K_Ic and fracture energy G_F^P-δ of IG11 graphite were determined and the FPZ length was quantitatively evaluated using the strain thresholds. The FPZ initiated at 55 % of the peak load and preceded the crack initiation. The evolution of the FPZ showed three phases and reached the maximum at approximately 75 % of P_c in post-peak stage with a length of 8.43 ± 0.41 mm. The obtained K_R-curves showed typical three stages: an initial rise, a stable plateau and a final decrease. The effect of the FPZ length on K_R-curve behavior was discussed and factors affecting the behavior of the K_R-curve were analyzed, including the length of the bridging zone, the test type and the grain size.

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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.