中子辐照超细晶奥氏体不锈钢的显微组织演变

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.2025.155710

Frederic Habiyaremye , Solène Rouland , Bertrand Radiguet , Fabien Cuvilly , Benjamin Klaes , Benoit Tanguy , Joël Malaplate , Christophe Domain , Diogo Goncalves , Marina M. Abramova , Nariman A. Enikeev , Xavier Sauvage , Auriane Etienne

{"title":"中子辐照超细晶奥氏体不锈钢的显微组织演变","authors":"Frederic Habiyaremye , Solène Rouland , Bertrand Radiguet , Fabien Cuvilly , Benjamin Klaes , Benoit Tanguy , Joël Malaplate , Christophe Domain , Diogo Goncalves , Marina M. Abramova , Nariman A. Enikeev , Xavier Sauvage , Auriane Etienne","doi":"10.1016/j.jnucmat.2025.155710","DOIUrl":null,"url":null,"abstract":"<div><div>Austenitic stainless steels utilized in-core components of pressurized water reactors are prone to radiation-induced segregation, which leads to the degradation of microstructure and mechanical properties. To improve irradiation resistance, one possible solution is to increase the number density of point defect sinks, such as grain boundaries. For this purpose, ultrafine-grained or nanostructured microstructures are recommended due to their high density of grain boundaries. This paper investigates the microstructural changes in ultrafine-grained 316 austenitic stainless steel exposed to neutron radiation up to 3.9 dpa in irradiation conditions representative of light water reactors. The microstructure at different length scales was analyzed using electron backscattered diffraction, transmission electron microscopy, and atom probe tomography before and after neutron irradiation. The study compares its findings with those of existing literature on coarse-grained austenitic stainless steels to evaluate the benefit of ultrafine-grained 316 austenitic stainless steels regarding irradiation ageing in representative conditions of light water reactors.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"607 ","pages":"Article 155710"},"PeriodicalIF":2.8000,"publicationDate":"2025-03-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Microstructural evolution of neutron irradiated ultrafine-grained austenitic stainless steel\",\"authors\":\"Frederic Habiyaremye , Solène Rouland , Bertrand Radiguet , Fabien Cuvilly , Benjamin Klaes , Benoit Tanguy , Joël Malaplate , Christophe Domain , Diogo Goncalves , Marina M. Abramova , Nariman A. Enikeev , Xavier Sauvage , Auriane Etienne\",\"doi\":\"10.1016/j.jnucmat.2025.155710\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>Austenitic stainless steels utilized in-core components of pressurized water reactors are prone to radiation-induced segregation, which leads to the degradation of microstructure and mechanical properties. To improve irradiation resistance, one possible solution is to increase the number density of point defect sinks, such as grain boundaries. For this purpose, ultrafine-grained or nanostructured microstructures are recommended due to their high density of grain boundaries. This paper investigates the microstructural changes in ultrafine-grained 316 austenitic stainless steel exposed to neutron radiation up to 3.9 dpa in irradiation conditions representative of light water reactors. The microstructure at different length scales was analyzed using electron backscattered diffraction, transmission electron microscopy, and atom probe tomography before and after neutron irradiation. The study compares its findings with those of existing literature on coarse-grained austenitic stainless steels to evaluate the benefit of ultrafine-grained 316 austenitic stainless steels regarding irradiation ageing in representative conditions of light water reactors.</div></div>\",\"PeriodicalId\":373,\"journal\":{\"name\":\"Journal of Nuclear Materials\",\"volume\":\"607 \",\"pages\":\"Article 155710\"},\"PeriodicalIF\":2.8000,\"publicationDate\":\"2025-03-01\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"0\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Journal of Nuclear Materials\",\"FirstCategoryId\":\"5\",\"ListUrlMain\":\"https://www.sciencedirect.com/science/article/pii/S0022311525001059\",\"RegionNum\":2,\"RegionCategory\":\"工程技术\",\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"Q3\",\"JCRName\":\"MATERIALS SCIENCE, MULTIDISCIPLINARY\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Journal of Nuclear Materials","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0022311525001059","RegionNum":2,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q3","JCRName":"MATERIALS SCIENCE, MULTIDISCIPLINARY","Score":null,"Total":0}

引用次数: 0

摘要

压水堆堆芯构件中使用的奥氏体不锈钢容易发生辐射偏析，导致其显微组织和力学性能下降。为了提高耐辐照性，一个可能的解决方案是增加点缺陷下沉的数量密度，如晶界。为此，推荐使用超细晶或纳米结构的微结构，因为它们的晶界密度高。研究了超细晶316奥氏体不锈钢在轻水堆辐照条件下受到3.9 dpa中子辐射后的显微组织变化。利用电子背散射衍射、透射电镜、原子探针层析成像等方法分析了中子辐照前后不同长度尺度下的微观结构。该研究将其研究结果与现有文献中粗晶奥氏体不锈钢的研究结果进行比较，以评估超细晶316奥氏体不锈钢在轻水反应堆代表性条件下辐照时效的效益。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

Microstructural evolution of neutron irradiated ultrafine-grained austenitic stainless steel

查看原文本刊更多论文

Microstructural evolution of neutron irradiated ultrafine-grained austenitic stainless steel

Austenitic stainless steels utilized in-core components of pressurized water reactors are prone to radiation-induced segregation, which leads to the degradation of microstructure and mechanical properties. To improve irradiation resistance, one possible solution is to increase the number density of point defect sinks, such as grain boundaries. For this purpose, ultrafine-grained or nanostructured microstructures are recommended due to their high density of grain boundaries. This paper investigates the microstructural changes in ultrafine-grained 316 austenitic stainless steel exposed to neutron radiation up to 3.9 dpa in irradiation conditions representative of light water reactors. The microstructure at different length scales was analyzed using electron backscattered diffraction, transmission electron microscopy, and atom probe tomography before and after neutron irradiation. The study compares its findings with those of existing literature on coarse-grained austenitic stainless steels to evaluate the benefit of ultrafine-grained 316 austenitic stainless steels regarding irradiation ageing in representative conditions of light water reactors.

求助全文

通过发布文献求助，成功后即可免费获取论文全文。去求助

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.