Page 17 - 《爆炸与冲击》2026年第10期
P. 17

第 46 卷    第 10 期                  爆    炸    与    冲    击                      Vol. 46, No. 10
                2026 年 10 月                   EXPLOSION AND SHOCK WAVES                          Oct., 2026

               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                                         *


                                 叶想平,王    静,杨兴据,吴凤超,耿华运,胡建波,俞宇颖,汤铁钢

                       (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)

                  摘要: 反应堆在服役过程中,其大量结构金属在预应力条件下受到高能粒子的辐照,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,降低反应堆的安全性与可靠性。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,并对后续研究应重点关注的科学问题和亟待突
               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。
                  关键词: 辐照损伤;预应力;应变率;力学性能;微观机理
                  中图分类号: O389; O346.1   国标学科代码: 13035; 13015   文献标志码: A

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


                              YE Xiangping, WANG Jing, YANG Xingju, WU Fengchao, GENG Huayun,
                                            HU Jianbo, YU Yuying, TANG Tiegang
                           (National Key Laboratory for Shock Wave and Detonation Physics, Institute of Fluid Physics,
                                 China Academy of Engineering Physics, Mianyang 621999, Sichuan, China)

               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



                 *   收稿日期: 2025-10-28;修回日期: 2026-05-12
                   基金项目: 国家自然科学基金(12475285,12105272,12202418)
                   第一作者: 叶想平(1986— ),男,博士,副研究员,yxpxiaogao13@163.com
                   通信作者: 汤铁钢(1974— ),男,博士,研究员,ttg1974@163.com


                                                         101101-1
   12   13   14   15   16   17   18   19   20   21   22