IMR OpenIR
Mechanical Properties and Microstructures of the HAZs of 11Cr F/M Steel for Gen-IV Nuclear Power Station
Y. K.; Wang Li, J.; Lu, S. P.; Rong, L. J.; Li, D. Z.
2015
发表期刊Journal of Materials Engineering and Performance
ISSN1059-9495
卷号24期号:2页码:885-893
摘要The weldability of a newly developed 11Cr ferritic/martensitic (F/M) steel to be used in Pb-Bi liquid cooled ADS for the fourth generation nuclear power station was studied by experiments and numerical simulation. In this work, an appropriate method for obtaining simulated heat-affected zones (HAZs) was developed. HAZs, including CG-HAZ, FG-HAZ, and IC-HAZ, were successfully simulated by Gleeble at heating rates of 209, 176, and 149 A degrees C/s and peak temperatures of 1314, 1138, and 998 A degrees C, respectively. Results of tension and impact tests indicated that the simulated HAZs had much higher strength and poorer toughness than the base metal. The poor toughness is caused by high carbon, silicon contents, and quenched martensitic microstructures. The tempering treatment is necessary for the developed steel before application in nuclear reactor.
部门归属[li, yongkui ; wang, jian ; lu, shanping ; rong, lijian ; li, dianzhong] chinese acad sci, shenyang natl lab mat sci, inst met res, shenyang 110016, peoples r china. ; li, yk (reprint author), chinese acad sci, shenyang natl lab mat sci, inst met res, 72 wenhua rd, shenyang 110016, peoples r china. ; ykli@imr.ac.cn ; shplu@imr.ac.cn
关键词11cr F/m Steel Finite Element Method Gen-iv Nuclear Materials Heat-affected Zones Thermal Simulation Heat-affected Zone Residual-stress Reactors Toughness
URL查看原文
文献类型期刊论文
条目标识符http://ir.imr.ac.cn/handle/321006/73853
专题中国科学院金属研究所
推荐引用方式
GB/T 7714
Y. K.,Wang Li, J.,Lu, S. P.,et al. Mechanical Properties and Microstructures of the HAZs of 11Cr F/M Steel for Gen-IV Nuclear Power Station[J]. Journal of Materials Engineering and Performance,2015,24(2):885-893.
APA Y. K.,Wang Li, J.,Lu, S. P.,Rong, L. J.,&Li, D. Z..(2015).Mechanical Properties and Microstructures of the HAZs of 11Cr F/M Steel for Gen-IV Nuclear Power Station.Journal of Materials Engineering and Performance,24(2),885-893.
MLA Y. K.,et al."Mechanical Properties and Microstructures of the HAZs of 11Cr F/M Steel for Gen-IV Nuclear Power Station".Journal of Materials Engineering and Performance 24.2(2015):885-893.
条目包含的文件
条目无相关文件。
个性服务
推荐该条目
保存到收藏夹
查看访问统计
导出为Endnote文件
谷歌学术
谷歌学术中相似的文章
[Y. K.]的文章
[Wang Li, J.]的文章
[Lu, S. P.]的文章
百度学术
百度学术中相似的文章
[Y. K.]的文章
[Wang Li, J.]的文章
[Lu, S. P.]的文章
必应学术
必应学术中相似的文章
[Y. K.]的文章
[Wang Li, J.]的文章
[Lu, S. P.]的文章
相关权益政策
暂无数据
收藏/分享
所有评论 (0)
暂无评论
 

除非特别说明,本系统中所有内容都受版权保护,并保留所有权利。