辐照-预应力和冲击耦合作用下金属硬化和脆化规律与微观机理实验研究进展

叶想平; 王静; 杨兴据; 吴凤超; 耿华运; 胡建波; 俞宇颖; 汤铁钢

doi:10.11883/bzycj-2025-0352

辐照-预应力和冲击耦合作用下金属硬化和脆化规律与微观机理实验研究进展

doi: 10.11883/bzycj-2025-0352

中国工程物理研究院流体物理研究所冲击波物理与爆轰物理全国重点实验室，四川绵阳 621999

基金项目: 国家自然科学基金（12475285，12105272，12202418）

详细信息

作者简介:
叶想平（1986—　），男，博士，副研究员，yxpxiaogao13@163.com

通讯作者:
汤铁钢（1974—　），男，博士，研究员，ttg1974@163.com

中图分类号: O389
计量
- 文章访问数: 190
- HTML全文浏览量: 23
- PDF下载量: 35
- 被引次数: 0
出版历程
- 收稿日期: 2025-10-28
- 修回日期: 2026-05-12
- 网络出版日期: 2026-05-15

Experimental advances in hardening, embrittlement and micro-mechanisms of metals under coupled irradiation, pre-stress and impact loading

National Key Laboratory for Shock Wave and Detonation Physics, Institute of Fluid Physics, China Academy of Engineering Physics, Mianyang 621999, Sichuan, China

摘要

摘要: 反应堆在服役过程中存在大量结构金属在预应力条件下被高能粒子辐照，同时还可能遭遇不可预知的冲击载荷，导致结构金属的力学性能发生显著退化，降低反应堆的安全与可靠。然而现有研究大多仅单独关注辐照或冲击效应对金属力学性能的影响规律与机理，较少研究辐照金属动力学的退化行为，更是极少考虑预应力这种典型工况的耦合影响效应。本文总结和评述了辐照、预应力和冲击载荷耦合作用下金属硬化与脆化性能的变化规律与微观机理实验研究现状，指出了当前研究中存在的不足与诸多挑战，并对后续研究需重点关注的科学问题和亟需突破的技术瓶颈等提出了意见和建议。希望为反应堆延寿与新型先进反应堆研发等大型国家工程建设涉及的辐照-预应力条件下金属硬化和脆化规律与机理研究提供科学依据与研究方法。
- 辐照损伤 /
- 预应力 /
- 应变率 /
- 力学性能 /
- 微观机理
Abstract: During service, numerous structural metals in nuclear reactors are subjected to high-energy particle irradiation under prestressed conditions and may also experience unpredictable impact loads. These conditions can lead to significant degradation of the mechanical properties of structural metals, including irradiation hardening, irradiation embrittlement, irradiation swelling, and irradiation creep, thereby reducing reactor safety and reliability. However, existing studies have predominantly focused on the effects of either irradiation or impact loading on the mechanical properties and deformation mechanisms of metals. A limited number of studies have investigated the degradation behavior of irradiated metals under dynamic loading, whereas the coupled effect of prestress, which is a typical reactor service condition, has been considered even less frequently. The current status of experimental research on the hardening and embrittlement behavior and underlying micromechanisms of metals subjected to the coupled effects of irradiation, prestress, and impact loading is reviewed and summarized. Shortcomings and major challenges in current research are identified, and perspectives and recommendations are proposed regarding the key scientific issues requiring further attention and the critical technological bottlenecks that must be overcome in future studies. Specifically, the following issues should be addressed: (1) the necessity and sufficiency of the causal relationship between dislocation channels and irradiation-induced hardening and embrittlement mechanisms require thorough investigation; (2) equivalent dose-rate assessment methods for metal hardening and embrittlement induced by different irradiation particle sources need to be strengthened; (3) the hardening and embrittlement mechanisms of structural metals in nuclear reactors under prestress and neutron irradiation conditions require further investigation; and (4) research on the impact behavior of prestressed and neutron-irradiated metals urgently needs to be initiated, while safe and efficient experimental techniques for characterizing the dynamic properties of neutron-irradiated metals must be developed immediately. This review is expected to provide a scientific basis and research methodology for future investigations into the hardening and embrittlement behavior and mechanisms of metals under irradiation-prestress conditions, as required in major national projects such as nuclear reactor life extension and the development of advanced reactors.
- irradiation damage /
- pre-stress /
- strain rate /
- mechanical properties /
- microscopic mechanisms

HTML全文

图 1 辐照缺陷生成与演化典型过程示意图^[54]

Figure 1. Schematic of radiation-induced defect generation and evolution processes^[54]

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图 2 中子辐照金属材料的准静态拉伸性能

Figure 2. Quasi-static tensile properties of neutron irradiation metallic materials

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图 3 中子辐照退火态BCC、FCC和HCP金属的准静态拉伸实验结果^[38]

Figure 3. Quasi-static tensile results of neutron irradiation annealed BCC、FCC and HCP metals^[38]

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图 4 中子辐照高纯铝应变平移后的真应力-应变曲线^[31]

Figure 4. Shifted true stress-strain curves of neutron irradiation high-purity aluminum^[31]

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图 5 中子辐照零应力无氧铜的微结构演化^[7]

Figure 5. Microstructure evolution of neutron irradiation OFHC^[7]

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图 6 辐照高熵合金的力学性能^[84,93,95]

Figure 6. Mechanical properties of irradiated high-entropy alloys^[84,93,95]

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图 7 不同剂量率He+辐照钨中位错环的尺寸与数密度TEM图^[104]

Figure 7. TEM diagrams of the size and density of dislocation loop in He+ irradiated tungsten at different dose rates^[104]

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图 8 中子注量率对低铜反应堆压力容器钢屈服强度的影响规律^[111]

Figure 8. Effect of Neutron flux rate on yield strength of low copper RPV steel^[111]

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图 9 辐照不锈钢应力～应变曲线^[26]

Figure 9. Engineering stress-strain curve of irradiated stainless steel^[26]

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图 10 中子辐照预拉伸应力退火态高纯铝的实验结果^[21]

Figure 10. Experimental results of neutron irradiation pre-stressed annealed high-purity aluminum^[21]

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图 11 预拉伸应力中子辐照退火态316不锈钢中缺陷分布^[12]

Figure 11. The distribution of defects in irradiation pre-tension stressed 316 annealed stainless steel^[12]

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图 12 沿位错环外法向分解主应力对位错环数密度的影响^[20]

Figure 12. Effect of principal stress decomposition along the outer normal direction of dislocation loops on dislocation loop number density^[20]

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图 13 滑移位错绕行通过不同取向性分布位错环时最小弓弯半径示意图^[21]

Figure 13. Schematic of dislocation bypassing hard obstacles with different distributions at critical time^[21]

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图 14 中子辐照不锈钢的典型落锤冲击实验断口形貌特征^[112]

Figure 14. Typical fracture surface of neutron-irradiated stainless steel in drop-weight impact tests^[112]

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图 15 中子辐照退火态304L钢的实验结果^[29]

Figure 15. Experimental results of neutron irradiation annealed 304L steel^[29]

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图 16 中子辐照退火态高纯铝的拉伸实验结果^[33]

Figure 16. Tensile experimentals of neutron irradiation annealed high-purity aluminum^[33]

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