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作 者:张宪龙 吕康源 丁兆楠 陈宇光 杨义涛[1] 张崇宏[1] 刘向兵[2] 薛飞[2] ZHANG Xian-long;LYU Kang-yuan;DING Zhao-nan;CHEN Yu-guang;YANG Yi-tao;ZHANG Chong-hong;LIU Xiang-bing;XUE Fei(Institute of Modern Physics,Chinese Academy of Sciences,Lanzhou 730000,China;Life Management Technology R&D Center of Suzhou Nuclear Power Research Institute Co.,Ltd.,Suzhou 215004,China)
机构地区:[1]中国科学院近代物理研究所,兰州730000 [2]苏州热工研究院有限公司寿命管理技术研发中心,江苏苏州215004
出 处:《装备环境工程》2022年第1期45-49,共5页Equipment Environmental Engineering
基 金:国家重点研发计划(2017YFB0702202)。
摘 要:目的采用小冲杆测试方法测量高能重离子辐照反应堆压力容器A508-3钢的辐照硬化和脆化特性,为工况条件下反应堆压力容器寿命预测提供实验依据。方法采用兰州重离子加速器提供的高能C^(6+)离子通过减能装置在290℃条件下开展A508-3钢辐照实验,并在样品表面形成一定厚度、准均匀分布的离位损伤层。通过开展不同辐照剂量辐照样品的小冲杆测试,得到不同辐照剂量A508-3钢的小冲杆载荷-位移曲线。通过对小冲杆测试得到的载荷-位移曲线的分析,测定不同辐照剂量样品的辐照硬化和脆化特性。结果压力容器A508-3钢辐照样品的硬化和脆化随着辐照剂量的增加逐渐增强,0.15 dpa以前呈线性增长,而后缓慢增大,约0.2 dpa时达到饱和趋势。结论通过小冲杆测试可以得到离子辐照样品的硬化和脆化行为,A508-3钢辐照硬化和脆化行为具有一致的变化趋势。The hardening and embrittlement characteristics of high-energy heavy-ions irradiated reactor pressure vessel A508-3 steel are measured by small punch test method,which provides experimental basis for the life prediction of reactor pressure vessel under working conditions.The high energy C^(6+)ions provided by Heavy Ion Research Facility are used to irradi ate A508-3 steel at 290℃by means of energy degrader,and a certain thickness of quasi-uniform damaged layer are formed on the sample surfaces.The load-displacement curves of A508-3 steel with different irradiation doses are obtained by small punch test.Through the analysis of the load-displacement curves obtained from the small punch test,the irradiation hardening and embrittlement characteristics of the samples with different irradiation doses are determined.The hardening and embrittlement of A508-3 steel increased with the increase of irradiation dose.It showed a linear increase before 0.15dpa,then increased slowly,and reached saturation at about 0.2dpa.The change trend of radiation hardening and embrittlement is consistent.
关 键 词:反应堆压力容器钢 重离子辐照 小冲杆测试 辐照硬化 辐照脆化
分 类 号:TG172[金属学及工艺—金属表面处理]
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