期刊文献+
任意字段
题名或关键词
题名
关键词
文摘
作者
第一作者
机构
刊名
分类号
参考文献
作者简介
基金资助
栏目信息

Zr-2.5Nb合金在550℃/25MPa超临界水中腐蚀时的氢致α/β相变 被引量：2

α/β Phase Transformation of Zr-2.5Nb Alloy Induced by Hydrogen during Corrosion Testing in SCW at 550 ℃/25 MPa
在线阅读 下载PDF
导出
摘要 Zr-2.5Nb合金经β相水淬及冷轧变形后,再经过580℃/5h和650℃/2h的热处理,在静态高压釜中进行550℃/25MPa超临界水腐蚀实验。用电子显微镜研究了腐蚀前、后合金基体的显微组织。结果表明在550℃/25MPa超临界水中腐蚀到一定程度后,合金基体内会形成氢稳定的β-Zr相,同时合金元素Nb扩散进入该相,形成富Nb/H的β-Zr相。该相在降温过程中发生分解,形成ZrHx、α-Zr和Nb含量不同的Zr-Nb相组织。 The corrosion behavior for Zr-2.5Nb specimens heat-treated at 580 ℃/5 h and 650 ℃/2 h respectively after β-quenching and cold rolling have been investigated in 550 ℃/25 MPa supercritical water （SCW） by autoclave tests. The scanning electron microscopy （SEM） and high resolution transmission electron microscopy （HRTEM） equipped with an energy dispersion spectroscopy （EDS） were employed for examining the matrix microstructure of the specimens before and after corrosion tests. It was noted that the microstructure of the matrix for the alloy specimens were drastically changed after corrosion testing for a certain period. It is considered that H-stabilized β-Zr were formed during corrosion testing at 550 ℃, and at the same time the Nb alloying element diffused into the β-Zr to form Nb/H-enriched β-Zr, which decomposed to ZrHx, α-Zr and Nb-enriched Zr-Nb phases as the corrosion temperature decreased.
作者 李强 周邦新 姚美意 刘文庆 褚于良
机构地区 上海大学
出处 《稀有金属材料与工程》 SCIE EI CAS CSCD 北大核心 2008年第10期1815-1818,共4页 Rare Metal Materials and Engineering
基金 上海市重点学科建设资助(T0101) 国家自然科学基金(50571056)资助
关键词 Zr-2.5Nb合金 超临界水 吸氢 相变 Zr-2.5Nb alloy supercritical water corrosion phase transformation
分类号 TG146.414 [金属学及工艺—金属材料]
  • 相关文献

参考文献8

  • 1Abrams Bobby, Chapin Douglas, Garrick B John et al. A Technology Roadmap for Generation IV Nuclear Energy Systems, US: DOE Nuclear Energy Research Advisory Committee, [2002-12], Http://www.nuclear.gov
  • 2Danielyan Davit. Supercritical- Water-Cooled Reactor Systemas One of the Most Promising Type of Generation IV Nuclear Reactor Systems, [2003-12-24], Http://www.nuclear.gov
  • 3Oka Yoshiaki, Koshizuka Seiichi. Journal of Nuclear Science and Technology[J], 2001, 38(12): 1081
  • 4Motta Arthur T, Jeong Yong Hwan. Advanced Corrosion-Resistant Zr Alloys for High Burn up and Generation IV Applications, Department of Energy International Nuclear Energy Research Initiative, DOE/ROK Project Number: [2003-020-K], Http://www.nuclear.gov
  • 5Li Qiang, Zhou Bangxin, Liu Wenqing et al. 15^th International Symposium on Zirconium in the Nuclear Industry[C], Sunriver, Oregon, USA, 2007
  • 6Jeong Y H, Park J Y, Gartner E et al. 15^th International Symposium on Zirconium in the Nuclear Industry[C], Sunriver, Oregon, USA, 2007
  • 7李强,周邦新,姚美意,刘文庆,褚于良.锆合金在550℃,25MPa超临界水中的腐蚀行为[J].稀有金属材料与工程,2007,36(8):1358-1361. 被引量：13
  • 8李强,刘文庆,周邦新.变形及热处理对Zr-Sn-Nb合金中β-Zr分解的影响[J].稀有金属材料与工程,2002,31(5):389-392. 被引量：33

二级参考文献10

  • 1雷鸣,刘文庆,严青松,李强,姚美意,周邦新.变形及热处理对Zr-Sn-Nb新锆合金第二相粒子的影响[J].稀有金属材料与工程,2007,36(3):467-470. 被引量：16
  • 2Kim H G,Kim T H,Jeong Y H.Nucl Mat[J],2002,306:44
  • 3Bobby Abrams,Douglas Chapin,John Garrick B et al.A Technology Roadmap for Generation Ⅳ Nuclear Energy Systems.U.S.DOE Nuclear Energy Research Advisory Committe,www.nuclear.gov,December 2002
  • 4Davit Danielyan.Supercritical-Water-Cooled ReactorSystemAs One of the Most Promising Type of Generation Ⅳ Nuclear Reactor Systems.www.nuclear.gov,November 24,2003
  • 5Yoshiaki Oka,Seiichi Koshizuka.Journal of Nuclear Science and Technology[J],2001,38(12):1081
  • 6Arthur T Motta,Yong Hwan Jeong.Advanced CorrosionResistant Zr Alloys for High Burnup and Generation ⅣApplications,Department of Energy International Nuclear Energy Research Initiative DOE/ROK Project Number:www.nuclear.gov,2003-020-K
  • 7Yong Hwan Jeong,Hyun Gil Kim,To Hoon Kim.Nucl Mat[J],2003,317:1
  • 8ZhaoWenjin(赵文金) MiaoZhi(苗志) JiangHongman(蒋宏曼)etal.核动力工程,2002,22(2):124-124.
  • 9刘文庆,李强,周邦新.锆锡合金腐蚀转折机理的讨论[J].稀有金属材料与工程,2001,30(2):81-84. 被引量：14
  • 10李强,刘文庆,周邦新.变形及热处理对Zr-Sn-Nb合金中β-Zr分解的影响[J].稀有金属材料与工程,2002,31(5):389-392. 被引量：33

共引文献44

同被引文献14

  • 1Chakravartty J K, Dey G K, Banerjee S et al. JNucl Mater[J], 1995, 218:247.
  • 2Castaldelli L, Fizzotti C, Lunde L. Eighth International Symposium on Zirconium in the Nuclear Industry[C]. US: ASTM, 1982, 754:105.
  • 3Aylin Yilmazbayhan, Motta Arthur T, Comstock Robert J et at. J Nucl Mater[J], 2004, 324:6.
  • 4Yong Hwan Jeong, Jeong-Yong Park, Jong-Hyuk Baek et al. Technical Meeting on Behavior of High Corrosion Resistance Zr-based Alloys[C]. Buenos Aires, Argentina: The National Library, 2005.
  • 5Hyun Seon Hong, Moon Jae Sik, Kim Seon Jin et al. J Nucl Mater[J], 2001, 297:113.
  • 6Jeong-Yong Park, Choi Byung-Kwon, Yoo Seung Jo et al. J Nucl Mater[J], 2006, 359:59.
  • 7Li Q, Zhou Bangxin, Yao Meiyi et al. 15th International Symposium on Zirconium in the Nuclear Industry[C]. Sunriver, Oregon, USA, 2007.
  • 8Was G S, Ampornrat P, Gupta G, et al. Corrosion and Stress Corrosion Cracking in Supercritical Water[J]. Journal of Nuclear Materials, 2007, 371: 176-201.
  • 9Jeong-Yong Park , Byung-Kwon Choi, Yong Hwan Jeong, et al. Corrosion Behavior and Oxide Properties of Zr- 1.1 wt%Nb-0.05 wt%Cu Alloy[J]. Journal of Nuclear Materials, 2006, 359: 59-68.
  • 10ASTM-G2-88. Standard Test Method for Corrosion Testing of Products of Zirconium, Hafnium and their Alloys in Water at 680F or in Steam at 750F [S]. Annual Book of ASTM Standards, 1992.

引证文献2

二级引证文献6

稀有金属材料与工程
2008年 第10期

相关作者

内容加载中请稍等...

相关机构

内容加载中请稍等...

相关主题

内容加载中请稍等...

浏览历史

内容加载中请稍等...
;
使用帮助 返回顶部