Nb稳定化奥氏体不锈钢在第四代核电领域的研究进展
收稿日期: 2025-07-15
修回日期: 2025-09-03
网络出版日期: 2025-12-18
基金资助
中国科学院战略性先导科技专项(XDA0410000);中核集团领创科研项目
Research Progress of the Niobium-Stabilized Austenitic Stainless Steels for Generation-IV Nuclear Reactors
Received date: 2025-07-15
Revised date: 2025-09-03
Online published: 2025-12-18
Supported by
Strategic Priority Research Program of Chinese Academy of Sciences(XDA0410000);LingChuang Research Project of China National Nuclear Corporation
奥氏体不锈钢因其良好的综合性能、成熟的制造工艺以及在压水反应堆中数十年的服役经验，是第四代核电反应堆核心部件的候选材料。然而，在长期高温、强辐照环境下，奥氏体不锈钢暴露出蠕变强度不足、组织稳定性较差、辐照脆化敏感性较高等不足。近年来，Nb元素的合金化可有效调控奥氏体不锈钢的第二相析出行为及辐照缺陷的形成和演化过程，有望实现高温蠕变性能与抗辐照性能的同步提升，成为开发新一代耐高温、抗辐照、长寿命奥氏体不锈钢的重要途径。本文系统综述了Nb稳定化奥氏体不锈钢在四代核电领域的研究进展，重点从高温蠕变性能和抗辐照性能提升的角度，回顾了其成分设计与优化的发展历程及应用现状，分析了Nb添加对奥氏体稳定性、初生NbC形成机制以及含Nb第二相析出和强化机制的影响，探讨了其对强韧性、蠕变强度、高温组织稳定性、辐照诱发缺陷演化的调节机制，并对未来Nb稳定化奥氏体不锈钢的发展进行了展望。
陈胜虎 , 谢昂 , 杨彬彬 , 刘涌涛 , 陈思含 , 赵明久 , 姜海昌 , 戎利建 . Nb稳定化奥氏体不锈钢在第四代核电领域的研究进展[J]. 金属学报, 2026 , 62(7) : 1175 -1188 . DOI: 10.11900/0412.1961.2025.00203
Austenitic stainless steels are utilized in the in-core and out-of-core structural components of various Generation-IV nuclear reactors owing to their excellent comprehensive properties, mature manufacturing processes, and decades of service experience in pressurized water reactors. However, after prolonged exposure to high temperature and high-intensity irradiation, these steels gradually exhibit some performance limitations, including lower creep strength, inadequate microstructural stabilities, and higher radiation embrittlement sensitivities. Recently, alloying with Nb has been proven to effectively regulate the precipitation behavior of secondary phases and the formation and evolution of irradiation defects in austenitic stainless steels, promising simultaneous improvements in creep strength and irradiation tolerance. Therefore, Nb alloying has emerged as a key pathway for the development of next-generation austenitic stainless steels with enhanced high-temperature performance, improved irradiation resistance, and extended service life. This paper systematically reviews the research progress of Nb-stabilized austenitic stainless steels for Generation-IV nuclear power applications, including the compositional design and optimization to improve the creep properties and irradiation resistance, the effects of Nb addition on austenite stability, the formation mechanisms of primary NbC, and the precipitation behavior of Nb-bearing secondary phases. Additionally, the mechanisms by which Nb alloying influences the strength-ductility balance, creep strength, high-temperature microstructural stability, and irradiation-induced defect evolution are discussed. Finally, some future research prospects of Nb-stabilized austenitic stainless steels for Generation-IV nuclear reactors are discussed.
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