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钠冷快堆组件结构材料发展概述

The Development of Structural Materials for Sodium-cooled Fast Reactor Components
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摘要 文章主要介绍的是钠冷快堆燃料组件的结构材料的发展现状。包壳材料从最初的316奥氏体钢,最终的发展方向是ODS铁素体/马氏体钢;外套管从最初的316奥式体钢,最终发展方向同样是ODS钢。材料的性能得到提高,组件结构材料性能的提高也将提高燃料组件的燃耗水平,并直接提高反应堆的安全性和经济性。 This article mainly introduces the development of structural materials for sodium -cooled fast reactor fuelassemblies.The initial cladding material is 316 austenitic steel and the final direction of development is ODS ferrite/martensitic steel.The initial wrapper tube is 316 Austenitic steel,the final direction of development is also ODS steel.Theperformance of the material is improved,and it will increase the fuel burnup levels.And directly improve the safety andeconomy of the reactor
作者 樊翔宇
机构地区 中国原子能科学研究院
出处 《科技视界》 2017年第29期82-83,共2页 Science & Technology Vision
关键词 快堆 组件 包壳管 外套管 Fast reactor Components Cladding tube Wrapper tube
分类号 TL352 [核科学技术—核技术及应用]
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  • 1A Alamo, V Lambard, M H Mathon, et al. Effects of the fabrication route on the microstructure and mechanical behaviourof ODS-14% Cr ferritic alloy including neutron irradiation performances [C] . International Symposium on < Application of Nanoparticle Dispersion Strengthening Steels to Advanced Nuclear Power Plant>, 6-7 Dec. 2003, Kyoto, Japan,.
  • 2T Kaito, T Narita, S Ukai, et al. High temperature oxidation behavior of ODS steels[J].Journal of Nuclear Materials, 2004,329-333 : 1388-1392.
  • 3Z Oksiuta, N Balue. Effect of mechanical alloying atmosphere on the microstructure and eharpy impact properties of an ODS ferritic steel [J]. Journal of Nuclear Materials, 2009,386-388 : 426-429.
  • 4Noriyuki Y Iwata, Tong Liu, Peng Dou. Et al. Effect of MA environment on the mechanical and microstructural properties of ODS ferritie steels[J]. Journal of Nuclear Materials , 2011.
  • 5S Yamashita, Seiichi Watanabe, Somei Ohnuki, et al. Effect of mechanical alloying parameters on irradiation damage in oxide dispersion strengthened ferritic steels[J].Journal of Nuclear Materials, 2000, 283-287: 647-651.
  • 6刘祖铭,张刘杰,刘咏,等.氧化物弥散强化铁基高温合金研究现状[C].2009全国粉末冶金学术会议论文集,45-51.
  • 7De Castro V, Leguey T, Munoz A, et al. Mechanical and microstructural behaviour of Y2O30DS EUROFER 97[J]. Journal of Nuclear Materials, 2007, 367-370 (Part 1) :196-201.
  • 8Ukai S, Nishida T, Okada H, et al. Development of Oxide Dispersion Strengthened Ferrite Steels for FBR Core Application, (I) Improvement of Mechanical Properties by Recrystallization Processing [J].Journal of Nuclear Science and Technology, 1997, 34 (3) :256-263.
  • 9POlier, A Bougault, A Alamo, et al. Effects of the forming processes and Y2O3 content on ODS-Eurofer meehanical properties [ J ] . Journal of Nuclear Materials, 2009, 386-388: 561-563.
  • 10S Ohtsuka, S Ukai, M Fuiiwara. Nano-mesoscopic structural control in 9Cr-ODS ferritic/martensitic steels. Journal of Nuclear Materials, 2006, 351: 241-246.

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科技视界
2017年 第29期

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