期刊检索

  • 2019年第27卷
  • 2018年第26卷
  • 2017年第25卷
  • 2016年第24卷
  • 2015年第23卷
  • 2014年第22卷
  • 2013年第21卷
  • 2012年第20卷
  • 2011年第19卷
  • 2010年第18卷
  • 第1期
  • 第2期

主管单位 中华人民共和国
工业和信息化部
主办单位 中国材料研究学会
哈尔滨工业大学
主编 苑世剑 国际刊号ISSN 1005-0299 国内刊号CN 23-1345/TB

期刊网站二维码
微信公众号二维码
引用本文:陈禹希,陈东旭,张峻巍.ODS钢研究进展及其在核电领域的应用现状[J].材料科学与工艺,2019,27(3):29-34.DOI:10.11951/j.issn.1005-0299.20180134.
CHEN Yuxi,CHEN Dongxu,ZHANG Junwei.Current research status of oxide dispersion strengthened steel and its application to nuclear power plant[J].Materials Science and Technology,2019,27(3):29-34.DOI:10.11951/j.issn.1005-0299.20180134.
【打印本页】   【HTML】   【下载PDF全文】   查看/发表评论  下载PDF阅读器  关闭
←前一篇|后一篇→ 过刊浏览    高级检索
本文已被:浏览 157次   下载 211 本文二维码信息
码上扫一扫!
分享到: 微信 更多
ODS钢研究进展及其在核电领域的应用现状
陈禹希1,2,陈东旭1,2,张峻巍1,2
(1.辽宁科技大学 激光先进制造技术研发中心,辽宁 鞍山 114051;2.辽宁科技大学 材料与冶金学院,辽宁 鞍山 114051)
摘要:
氧化物弥散强化钢(Oxide Dispersion Strengthened Steel, ODS 钢),具有优异的力学性能、高温稳定性及抗辐照性能.本文概要地综述了机械合金化、热等静压固化成形、等离子烧结及转角挤压等ODS钢的制备方法,总结了微观组织及结构对ODS钢性能的影响规律及影响机制,又综述了合金元素对ODS钢性能影响的相关研究进展;并对ODS 钢在核电领域中的应用及相关研究进展进行了概括,介绍了激光技术在ODS 钢制备及加工领域的应用,讨论了ODS 钢在核电环境服役过程中存在的主要问题及进一步的研究方向,为核电站的安全运行提供有力的参考依据,对于核电材料的创新发展具有一定的参考作用.
关键词:  氧化物弥散强化  核电材料  机械合金化  抗辐照损伤  激光
DOI:10.11951/j.issn.1005-0299.20180134
分类号:TG406
文献标识码:A
基金项目:辽宁省自然科学基金资助项目(2015020226).
Current research status of oxide dispersion strengthened steel and its application to nuclear power plant
CHEN Yuxi1,2, CHEN Dongxu1,2, ZHANG Junwei1,2
(1.Research & Design Center for Advanced Laser Manufacturing Technology, University of Science and Technology Liaoning, Anshan 114051, China; 2. School of Materials and Metallurgy, University of Science and Technology Liaoning, Anshan 114051, China)
Abstract:
Oxide dispersion strengthened (ODS) steel has received more and more attention from researchers, because of its excellent mechanical properties, high temperature stability, and radiation resistance. In nuclear power industry, ODS steel has become a candidate material for the fourth-generation nuclear reactor, especially for the first wall cladding material and high-temperature structural material such as supercritical water cooled reactor (SCWR). It has also been included in the corresponding SCWR material R & D planning. The manufacturing methods of ODS steel like mechanical alloying, hot isostatic pressing, plasma sintering, and corner extrusion were briefly reviewed. Effects of microstructures on the properties of ODS steel and its influence mechanism were summarized. Moreover, the research progress of the influence of alloying elements on the properties of ODS steel was summed up. The application of ODS steel in nuclear power and its related research progress were summarized. The application of laser technology in the processing of ODS steel was introduced. The main problems of ODS steel during service in nuclear power environment were discussed. The further possible research topics and directions were proposed, which provides a reliable reference for the safe operation of nuclear power plants and is helpful for the innovative development of nuclear power materials.
Key words:  oxide dispersion strengthening  nuclear power material  mechanical alloying  anti-irradiation damage  laser

友情链接LINKS