Investigation on the SCC susceptibility of a heat-optimized l-PBF 304L stainless steel in simulated primary water

IF 3.2 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY Journal of Nuclear Materials Pub Date : 2025-02-07 DOI:10.1016/j.jnucmat.2025.155685

Kai Chen , Yuhao Zhou , Fawen Zhu , Shixin Gao , Quanyao Ren , Kun Zhang , Xiaoqing Shang , Lefu Zhang

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Abstract

This study examines the stress corrosion cracking (SCC) behavior of laser powder bed fusion (L-PBF) 304 L stainless steel after solution annealing (SA) in high-temperature water environments. SCC susceptibility was evaluated under both hydrogenated and oxygenated water environments at 325 °C and 15.5 MPa. The results showed that heat-treated l-PBF 304 L exhibited fully recrystallized equiaxed grains, characterized with high-density annealing twins and a uniform microstructure. Stress-strain tests revealed a marked reduction in elongation and mixed intergranular (IG) and transgranular (TG) cracking, indicating significant SCC susceptibility in both environments. Notably, hydrogenated water conditions led to a higher proportion of TG cracking, suggesting enhanced hydrogen embrittlement (HE), while oxygenated conditions favored IG cracking. Cross-sectional analysis highlighted localized strain concentration at crack tips, and precipitates were found to play a critical role in the initiation and propagation of cracks. These findings provide crucial insights into the relationship between microstructure, environmental factors, and SCC behavior in l-PBF 304 L stainless steel.

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热优化l-PBF 304L不锈钢在模拟原生水中SCC敏感性的研究

研究了激光粉末床熔合（L- pbf） 304 L不锈钢在高温水中溶液退火后的应力腐蚀开裂（SCC）行为。在325°C和15.5 MPa的氢化和氧化水环境下，对SCC敏感性进行了评估。结果表明：热处理后的L - pbf 304 L表现出完全再结晶的等轴晶粒，具有高密度退火孪晶和均匀的显微组织；应力-应变测试显示伸长率和混合晶间（IG）和穿晶（TG）裂纹显著降低，表明在这两种环境中都存在显著的SCC敏感性。值得注意的是，氢化水条件导致TG开裂比例更高，表明氢脆（HE）增强，而氧化条件有利于IG开裂。截面分析强调了裂纹尖端的局部应变集中，并且发现析出物在裂纹的萌生和扩展中起着关键作用。这些发现为L - pbf 304 L不锈钢的微观结构、环境因素和SCC行为之间的关系提供了重要的见解。

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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.