15-15Ti奥氏体不锈钢中D、He、Ne离子辐照损伤的TEM表征  

TEM Characterization of D,He,Ne Ion Irradiation Damage of 15-15Ti Austenitic Stainless Steel

作　　者：安瞻 徐驰 龚翱翔 佟振峰 AN Zhan;XU Chi;GONG Aoxiang;TONG Zhenfeng(School of Nuclear Science and Engineering,North China Electric Power University,Beijing 102206,China;Key Laboratory of Beam Technology of the Ministry of Education,School of Nuclear Science and Technology,Beijing Normal University,Beijing 100875,China)

机构地区：[1]华北电力大学核科学与工程学院,北京102206 [2]北京师范大学核科学与技术学院,射线束技术教育部重点实验室,北京100875

出　　处：《材料导报》2025年第6期173-178,共6页Materials Reports

基　　金：国家自然科学基金(12105017)。

摘　　要：15-15Ti奥氏体不锈钢因优异的力学性能、高温稳定性能、耐腐蚀性能和抗辐照性能而作为商用快堆包壳材料的候选材料之一。目前国内对15-15Ti奥氏体不锈钢的辐照损伤研究仍然较少,且辐照实验多采用较低的辐照剂量,与商用快堆内极高的辐照剂量所对应的实验数据更为欠缺。为探究商用快堆内极高的辐照剂量对15-15Ti奥氏体不锈钢辐照损伤的影响,给15-15Ti奥氏体不锈钢的抗辐照性能研究提供实验数据补充,选用D^(+)、He^(+)以及Ne^(+)对15-15Ti在较高与较低的辐照剂量下进行离子辐照实验,对辐照后样品的微观结构进行了TEM表征,统计分析了位错环、气泡等辐照缺陷的尺寸与密度。结果表明,随着辐照剂量的增加,位错环与空洞的尺寸明显增大,且数密度降低;在晶界与析出物边界附近有明显的空洞聚集现象;纳米压痕实验显示样品有明显的辐照硬化现象。15-15Ti austenitic stainless steel is one of the candidate materials for commercial fast reactor cladding materials due to its excellent mechani-cal properties,high temperature stability,corrosion resistance and radiation resistance.At present,there are still few studies on the irradia-tion damage of 15-15Ti austenitic stainless steel,and the irradiation experiment mostly uses a lower irradiation dose,the experimental data corre-sponding to the extremely high irradiation dose in the commercial fast reactor are even more lacking.In order to explore the effect of extremely high irradiation dose on the irradiation damage of 15-15Ti austenitic stainless steel in commercial fast reactor,the experimental data supplement for the irradiation resistance of 15-15Ti austenitic stainless steel was provided,the samples were irradiated with D^(+),He^(+)and Ne^(+)by using trans-mission electron microscopy and nano-indentation techniques.The microstructure of irradiated samples was characterized by TEM,and the size and density of irradiation defects such as dislocation loops and bubbles were statistically analyzed.The results show that with the increase of irra-diation dose,the size of dislocation loops and voids increases obviously,and the number density decreases.There is obvious void accumulation near the boundary between grain boundary and precipitate,and obvious irradiation hardening phenomenon.

关 键 词：15-15Ti奥氏体不锈钢 透射电子显微镜 纳米压痕 辐照损伤 

分 类 号：TL341[核科学技术—核技术及应用]