[1]陈驰,陈东钺,邱玺,等.微观缺陷演化驱动下钼铼合金辐照性能劣化[J].中国材料进展,2026,45(11):001-9.
　CHEN Chi,CHEN Dongyue,QIU Xi,et al.Irradiation Degradation of Molybdenum-Rhenium Alloy Driven by Microdefect Evolution[J].MATERIALS CHINA,2026,45(11):001-9.
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微观缺陷演化驱动下钼铼合金辐照性能劣化()

中国材料进展[ISSN:1674-3962/CN:61-1473/TG]

卷:
45
期数:
2026年11
页码:
001-9
栏目:
出版日期:
2026-10-31

文章信息/Info

Title:
Irradiation Degradation of Molybdenum-Rhenium Alloy Driven by Microdefect Evolution
作者:
陈驰;  陈东钺; 邱玺; 郭姗; 王丽婷; 吕沙沙; 李垣明; 李正操。
1 清华大学材料学院 北京 100084 2 中国核动力研究设计院 核反应堆技术全国重点实验室 四川成都610213
Author(s):
CHEN Chi;  CHEN Dongyue;  QIU Xi;  GUO Shan;  WANG Liting;  LV Shasha; LI Yuanming;  LI Zhengcao
1 School of Material Science, Tsinghua University, Beijing, 100084, China 2 Nuclear Power Institute of China, National Key Laboratory of Nuclear Reactor Technology, Chengdu, 610213, China
关键词:
钼铼合金; 辐照效应; 性能劣化; 微观缺陷; 微观机制
Keywords:
Molybdenum-Rhenium alloys;  irradiation effects;  performance degradation; microdefects;  Microscopic mechanism
分类号:
TG146.412
文献标志码:
A
摘要:
铼合金凭借其优异的高温力学性能、耐腐蚀性和加工性能，成为高温核反应堆堆芯结构材料及燃料包壳材料的候选材料之一。然而，钼铼合金在强辐照环境下面临显著的辐照硬化和脆化现象，严重地制约了其在高温堆内的应用。更关键的是，辐照肿胀和蠕变行为进一步加剧了材料失效的风险，导致体积膨胀和结构失稳，威胁反应堆的安全性和寿命。微观上，辐照产生大量缺陷团簇，后续演化形成位错环和空洞，同时辐照诱导偏析作用导致铼元素向缺陷势阱处偏聚形成第二相粒子，严重地影响着钼铼合金的宏观性能；宏观上，低辐照剂量即可引发显著的强度和塑性劣化，表现为屈服强度大幅升高、延伸率急剧下降及韧脆转变温度大幅升高。本文系统地综述了近几十年钼铼合金辐照性能微观与宏观的研究进展，针对钼铼合金中的微观缺陷进行了综述介绍，以及钼铼合金的辐照硬化和脆化行为、辐照蠕变行为和辐照肿胀行为。同时，分析了钼铼合金辐照损伤与微观辐照缺陷之间的联系与机制。最后，本文对钼铼合金辐照研究内容进行了总结与展望，以期为钼铼合金的设计优化和实际入堆应用提供理论参考。
Abstract:
Molybdenum-Rhenium (Mo-Re) alloys are prominent candidate materials for core structural components and fuel cladding in high-temperature nuclear reactors, owing to their exceptional high-temperature mechanical properties,corrosion resistance, and fabricability. However, Mo-Re alloys undergo significant radiation-induced hardening and embrittlement under intense irradiation environments, which severely restricts their application in high-temperature reactors. More critically, irradiation swelling and creep behaviors further exacerbate the risk of material failure, leading to volume expansion and structural instability, thereby threatening reactor safety and operational lifetime. At the microscopic level, irradiation generates a high density of defect clusters, which subsequently evolve into dislocation loops and voids. Concurrently, radiation-induced segregation (RIS) facilitates the enrichment of Re atoms at defect sinks, leading to the precipitation of second-phase particles, which significantly degrades the macroscopic performance of Mo-Re alloys. At the macroscopic level, even low irradiation doses can induce substantial degradation of strength and ductility, manifested by a sharp increase in yield strength, a drastic reduction in elongation, and a significant rise in the ductile-to-brittle transition temperature (DBTT). This paper provides a comprehensive review of the research progress regarding the microscopic and macroscopic irradiation performance of Mo-Re alloys over recent decades. The review focuses on the evolution of microscopic defects, as well as the behaviors of radiation-induced hardening, embrittlement, irradiation creep, and swelling. Furthermore, the correlations and underlying mechanisms between irradiation damage and microscopic defect evolution are analyzed. Finally, a summary and outlook for future research on Mo-Re alloys are presented to provide a theoretical basis for alloy design optimization and practical in-pile applications.
更新日期/Last Update: 2026-09-28