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中国腐蚀与防护学报  2026, Vol. 46 Issue (1): 1-14     CSTR: 32134.14.1005.4537.2025.273      DOI: 10.11902/1005.4537.2025.273
  增材制造与腐蚀专题 本期目录 | 过刊浏览 |
选区激光熔化奥氏体不锈钢高温高压水中应力腐蚀开裂行为研究进展
兰博韬1,2, 吴斌1,2(), 明洪亮1,2(), 王俭秋1,2, 韩恩厚1,3
1.中国科学院金属研究所 沈阳 110016
2.中国科学技术大学材料科学与工程学院 沈阳 110016
3.广东腐蚀科学与技术创新研究院 广州 510530
Research Progress of Stress Corrosion Crack Behavior of Selected Laser Melted Austenitic Stainless Steel in High Temperature Pressurized Water
LAN Botao1,2, WU Bin1,2(), MING Hongliang1,2(), WANG Jianqiu1,2, HAN En-Hou1,3
1.Institute of Metal Research, Chinese Academy of Sciences, Shenyang 110016, China
2.School of Materials Science and Engineering, University of Science and Technology of China, Shenyang 110016, China
3.Institute of Corrosion Science and Technology, Guangzhou 510530, China
引用本文:

兰博韬, 吴斌, 明洪亮, 王俭秋, 韩恩厚. 选区激光熔化奥氏体不锈钢高温高压水中应力腐蚀开裂行为研究进展[J]. 中国腐蚀与防护学报, 2026, 46(1): 1-14.
Botao LAN, Bin WU, Hongliang MING, Jianqiu WANG, En-Hou HAN. Research Progress of Stress Corrosion Crack Behavior of Selected Laser Melted Austenitic Stainless Steel in High Temperature Pressurized Water[J]. Journal of Chinese Society for Corrosion and protection, 2026, 46(1): 1-14.

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摘要: 

增材制造技术因其在复杂结构成型上的高灵活性,在核电领域具有广阔应用前景。然而,增材制造会导致材料内部形成独特的柱状晶、熔池边界等非均衡组织,进而对材料在高温高压水中的应力腐蚀开裂行为(SCC)产生显著影响。本文综述了选区激光熔化(SLM)增材制造不锈钢的组织结构特点及其SCC行为研究进展,重点分析了成分、组织结构差异及服役环境对SLM不锈钢SCC行为的影响规律和机制,并基于此讨论了现阶段SLM技术在核电领域应用过程中所面临的挑战与发展方向。

关键词 增材制造奥氏体不锈钢高温高压水应力腐蚀开裂裂纹萌生裂纹扩展    
Abstract

Additive manufacturing (AM), particularly selective laser melting (SLM), offers significant potential for nuclear power industry due to its ability to fabricate complex components with exceptional design flexibility. However, the inherent characteristics of the AM process produce unique, non-equilibrium microstructures, such as columnar grains and melten pool boundaries, which can significantly affect the stress corrosion crack (SCC) behavior in high temperature pressurized water. This paper provides a comprehensive review of the microstructural features and recent advances in understanding the SCC behavior of SLM stainless steel. Special attention is given to the governing roles of chemical composition, microstructural evolution, and service conditions on the SCC behavior of SLM stainless steels. Finally, the prevailing challenges and future perspectives for the application of SLM stainless steels in the nuclear power system are critically discussed.

Key wordsadditive manufacturing    austenitic stainless steel    high temperature pressurized water    stress corrosion crack    crack initiation    crack propagation
收稿日期: 2025-08-28      32134.14.1005.4537.2025.273
ZTFLH:  TG174  
基金资助:国家自然科学基金(U22B2067);中国核工业集团青年英才项目和中国科学院青年创新促进会(2022187)
通讯作者: 吴斌,E-mail:bwu18s@imr.ac.cn,研究方向为核用材料及构件的环境服役行为;
明洪亮,E-mail:hlming12s@imr.ac.cn,研究方向为能源/核电关键材料服役安全评价与寿命预测
作者简介: 兰博韬,2001年出生,2023年毕业于中南大学,获学士学位。现就读于中国科学技术大学,博士生。主要研究方向为增材制造不锈钢在高温高压水中的应力腐蚀行为。
吴斌,1996年9月生,2023年6月毕业于中国科学技术大学,获工学博士学位。现为中国科学院金属研究所副研究员,主要从事核能/氢能关键材料及构件的环境服役行为研究,包括,材料表面缺陷(划伤、肿胀等)的腐蚀及应力腐蚀行为、核电关键部件在高温高压超临界CO2下的腐蚀及应力腐蚀行为和力学-化学-辐照耦合损伤效应研究、临氢管线钢疲劳裂纹扩展智能化评价技术及失效机理研究等。主持国家自然科学基金青年基金、国家资助博士后研究人员计划、中核集团青年英才等项目5项;执行负责国家科技重大专项、中国科学院战略先导A等项目的课题和任务5项。以第一/通讯作者在Acta Materialia、Corrosion Science、Journal of Materials Science & Technology 和Journal of Nuclear Materials 等期刊发表论文15 篇;申请发明专利10项;主笔编制并发布中国核学会团体标准1项;曾获国家资助博士后研究人员计划,中国核工业集团有限公司“启明星人才”等奖励。
明洪亮,博士,中国科学院金属研究所研究员,2017年毕业于中国科学院大学。主要从事核电、氢能关键材料环境使役行为研究,发表论文90余篇,申请发明专利23项,编制行标1项、中国核学会团标14项,主持国家自然科学基金、中科院先导A课题等20余项项目,担任《中国腐蚀与防护学报》等5本期刊的编委/青年编委,获国际先进材料学会青年科学家奖章等;入选科技部重点领域创新团队核心成员、中科院青促会会员、中科院稳定支持基础研究领域青年团队、辽宁省“百千万人才工程”人才等。
图1  SLM材料的制备过程示意图[15]
图2  增材制造材料在不同尺度下的组织特征[8]
图3  SLM材料中的熔池边界形成过程示意图[18]及观察面平行于SLM材料构建方向时所观察到的熔池结构[17]
图4  SLM材料制备过程中粉末未完全熔化导致的结合缺陷[18,31]
图5  SLM材料制备过程中产生的气孔和层状空隙[31]
图6  材料应力腐蚀开裂过程示意图[50]
图7  690合金SCC裂纹萌生机理示意图[51]
图8  奥氏体不锈钢在288 ℃高温高压水中的电化学电位和溶解氧浓度的关系[99]
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