<strong>Nb</strong>稳定化奥氏体不锈钢在第四代核电领域的研究进展

doi:10.11900/0412.1961.2025.00203

金属学报

2026, Vol. 62

Issue (7): 1175-1188 DOI: 10.11900/0412.1961.2025.00203

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Nb稳定化奥氏体不锈钢在第四代核电领域的研究进展

陈胜虎¹^,²(

), 谢昂¹, 杨彬彬², 刘涌涛², 陈思含¹, 赵明久¹^,², 姜海昌¹^,², 戎利建¹^,²(

)

1 中国科学院金属研究所中国科学院核用材料与安全评价重点实验室沈阳 110016
2 中国科学技术大学材料科学与工程学院沈阳 110016

Research Progress of the Niobium-Stabilized Austenitic Stainless Steels for Generation-IV Nuclear Reactors

CHEN Shenghu¹^,²(

), XIE Ang¹, YANG Binbin², LIU Yongtao², CHEN Sihan¹, ZHAO Mingjiu¹^,², JIANG Haichang¹^,², RONG Lijian¹^,²(

)

1 CAS Key Laboratory of Nuclear Materials and Safety Assessment, 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

引用本文:

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.
Shenghu CHEN, Ang XIE, Binbin YANG, Yongtao LIU, Sihan CHEN, Mingjiu ZHAO, Haichang JIANG, Lijian RONG. Research Progress of the Niobium-Stabilized Austenitic Stainless Steels for Generation-IV Nuclear Reactors[J]. Acta Metall Sin, 2026, 62(7): 1175-1188.

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摘要:

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。

关键词 ： Nb稳定化奥氏体不锈钢, 强韧性匹配, 蠕变强度, 高温组织稳定性, 辐照诱发缺陷, 含Nb第二相

Abstract：

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.

Key words： niobium-stabilized austenitic stainless steel strength-ductility balance creep strength high-temperature microstructural stability irradiation-induced defect Nb-bearing secondary phase

收稿日期: 2025-07-15

ZTFLH:

TG142.25

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

通讯作者: 陈胜虎，chensh@imr.ac.cn，主要从事核用结构材料研究；
戎利建，ljrong@imr.ac.cn，主要从事特种合金研究

Corresponding author: CHEN Shenghu, professor, Tel: (024)23971981, E-mail: chensh@imr.ac.cn；

作者简介: 陈胜虎，男，1986年生，研究员，博士

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表1 六种第四代反应堆系统的服役工况[6~10]

表2 先进核电反应堆用含Nb奥氏体不锈钢的化学成分[44~46] (mass fraction / %)

图1 不同Nb含量Fe-15Cr-10Ni氏体不锈钢的铸态组织

图2 Nb含量对Fe-15Cr-10Ni奥氏体不锈钢中NbC析出行为的热力学模拟计算与含0.9%Nb铸态组织的OM像

图3 铸态试样中初生NbC和奥氏体的纳米压痕结果及室温变形后组织形貌的TEM像[62]

图4 Fe-15Cr-10Ni奥氏体不锈钢中初生NbC的三维分布形貌及室温冲击断裂后组织形貌的SEM像和Nb元素EDS面扫描图

图5 不同牌号奥氏体不锈钢的高温蠕变强度

图6 Alloy 709和HT-UPS奥氏体不锈钢经高温服役后的第二相形貌[76,77]及MC碳化物EDS分析

图7 316L钢和Nb稳定化20Cr25Ni奥氏体不锈钢的温度-时间-析出(TTP)曲线[80,81]

图8 Nb稳定化奥氏体不锈钢中G相和σ相形成机理示意图

图9 Nb添加对Fe-16Ni-15Cr合金50 dpa离子辐照条件下空洞密度和直径的影响[92]

图10 NbC/基体界面捕获点缺陷的微观机制[96]

图11 Nb稳定化奥氏体不锈钢的综合性能评估[104]

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