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12Cr-ODS钢中氧化物强化相(Y_2O_3)辐照损伤行为研究 被引量:3

Irradiation Damage Behavior of Oxide Dispersion Strengthened Phase in 12Cr-ODS Ferritic Steel
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摘要 本文采用电子束(e-)-氦离子(He+)、氢离子(H+)束同时复合辐照方式研究12Cr-ODS铁素体钢中氧化物弥散强化相(Y2O3)辐照损伤行为,对不同辐照方式下辐照区内的氧化物形貌变化进行原位观察。研究结果表明,15dpa辐照后,氧化物周围出现微小高密度空洞,相界面变得不规则,氧化物在此特定条件下发生体积收缩或长大,尺寸有少量变化,但无明显溶解现象,对钢的性能不会产生影响。 Irradiation damage behavior of oxide dispersion strengthened phase(Y2O3) in 12Cr-ODS ferrite steel was investigated by electron(e-)-helium ion(He+),hydrogen ion(H+) dual-beam irradiation.The morphology change of oxide in irradiation region was observed in-site at different irradiation models.The experiment results show that oxide size is not changed obviously under 15 dpa irradiation,however,high density small voids form surrounding oxide,and the phase boundaries are changed irregularly.The volume of oxide is shrank or expanded in the specified condition.The size of oxide is damaged lightly but not dissolved,which would not affect the performance of the steel.
出处 《原子能科学技术》 EI CAS CSCD 北大核心 2011年第3期319-323,共5页 Atomic Energy Science and Technology
基金 国家973计划资助项目(2007CB209800)
关键词 辐照损伤 氧化物稳定性 ODS钢 irradiation damage oxide particles stability ODS steel
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参考文献9

  • 1VERHIEST K, ALMAZOUZI A, WISPELAERE N D, et al. Development of oxides dispersion strengthened steels for high temperature nuclear reactor applications[J]. Journal of Nuclear Materials, 2009, 385(2): 308-311.
  • 2ALLEN T R, TAN L, GAN J, et al. Microstructural development in advanced ferritic martensitic steel HCM12A [J]. Journal of Nuclear Materials, 2006, 351(1 3).. 174-186.
  • 3DUBUSISSON P, SCHILL R, HUGON M P, et al. Behavior of an oxide dispersion strengthened ferritic steel irradiated in Phenix[C]//18th Inter national Symposium on Effects of Radiation in Materials. USA: [s. n.], 1999: 17-19.
  • 4MONNET I, DUBUSISSON P, DERRUYS Y, et al. Microstructural investigation of the stability under irradiation of oxide dispersion strength ened ferritic steels [J]. Journal of Nuclear Materials, 2004, 335(3): 311-321.
  • 5GAN J, ALLEN T R, BIRTCHER R C, et al.The development of metallic nuclear fuels for transmutation applications: Materials challenges [J]. Journal of Metals, 2008, 60(1): 24-28.
  • 6YOSHITAKE T, ABE Y, AKASAKA N, et al. Ring tensile properties of irradiated oxide disper sion strengthened ferritic/martensitic steel claddings [J]. Journal of Nuclear Materials, 2004, 329 333(1): 342-346.
  • 7AKASAKA N, YAMASHITA S, YOSHITAKE T, et al. Microstructural changes of neutron irradiated ODS ferritic and martensitic steels [J]. Journal of Nuclear Materials, 2004, 329- 333(2):1 053-1 056.
  • 8ALLEN T R, GAN J, COLE J I, et al. The stability of 9Cr-ODS oxide particles under heavy-ion irradiation[J]. Nuclear Science and Engineering, 2005, 151(3): 305-312.
  • 9BARIN I, KNACKE O. Thermochemical properties of inorganic substances[M]. Berlin, Heideberg, New York: Springer-Verlag, 1973.

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  • 2冯开明.可控核聚变与ITER计划[J].现代电力,2006,23(5):82-88. 被引量:19
  • 3洪文玉,严龙文,钱俊,赵开君,程均,罗萃文,徐征宇.HL-2A装置的ECRH实验和偏滤器特性[J].核聚变与等离子体物理,2007,27(1):7-11. 被引量:7
  • 4黄群英,李春京,李艳芬,刘少军,吴宜灿,李建刚,万发荣,巨新,单以银,郁金南,朱升云,张品源,杨建锋,韩福生,孔明光,李合琴,室贺健夫,长坂琢也.中国低活化马氏体钢CLAM研究进展[J].核科学与工程,2007,27(1):41-50. 被引量:97
  • 5Fan Jinglian(范景莲).Tungsten Alloy and Its Preparation Technology(钨合金及其制备新技术)[M].Beijing:Metallurgical Industry Press,2006.
  • 6Ge Changchun(葛昌纯),Zhang Yingchun(张迎春),Xu Yadong(徐亚东)et al.航天器环境工程[J],2010,27(1):13.
  • 7Mario Merola, Loesser D, Martina A et al. Fusion Engineering and Design [J], 2010, 85(6): 2312.
  • 8Philipps V. Journal of Nuclear Materials [J], 2011, 415: 2.
  • 9JOrg Hohe, Peter Gumbsch. Journal of Nuclear Materials[J], 2010, 400:218.
  • 10Matsui H, Fukumoto K, Smith D Let al. Journal of Nuclear Materials [J], 1996, 233-237:92.

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