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14YWT-ODS铁素体钢的高温稳定性 被引量:3

High temperature stability of 14 YWT-ODS ferritic alloy
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摘要 通过机械合金化(MA)和热等静压(HIP)技术制备14 YWT-ODS铁素体钢,将其分别在1100、1200和1300℃真空退火1 h并测试显微硬度,用原子探针层析技术(APT)对这些样品进行分析。结果表明,与HIP态样品相比,1100℃退火样品硬度略有降低,1200℃退火样品硬度下降明显,1300℃退火样品硬度显著下降;1100℃退火样品中Y-Ti-O纳米团簇大小未发生明显变化,高于1200℃退火时,样品中Y-Ti-O团簇粗化明显,数量密度显著降低。 Ferritic alloy Fe-14Cr-2W-0. 3Ti-0. 3Y2O3( 14 YWT-ODS) was prepared by mechanical alloying( MA) and hot isostatic pressing( HIP). The stability of the 14 YWT-ODS ferritic alloy after annealing at 1100,1200 and 1300 ℃ for 1 h was studied by microhardness test and atom probe tomography( APT) analysis. The results show that the microhardness of the specimen decreases slightly after annealing at 1100 ℃,while decreases obviously at 1200 ℃ and significantly at 1300 ℃. The APT results reveal that there is little difference between the as-HIPed specimen and the annealed specimen at 1100 ℃ in the size and number density of the Y-Ti-O-enriched particles,while annealing above 1200 ℃ coarsens the Y-Ti-O-enriched nanoclusters obviously in size and decreases significantly in the number density,which indicates that high temperature mechanical properties of 14YWT-ODS ferritic alloy result from the stability of Y-TiO-enriched nanoclusters.
出处 《材料热处理学报》 EI CAS CSCD 北大核心 2015年第7期139-143,共5页 Transactions of Materials and Heat Treatment
基金 上海市科学技术委员会重点项目(12JC1404000)
关键词 ODS铁素体钢 Y-Ti-O纳米团簇 原子探针层析技术 稳定性 ODS ferritc alloys Y-Ti-O-enriched nanoclusters atom probe tomography stability
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参考文献17

  • 1Odette G R,Alinger M J,Wirth B D. Recent developments in irradiation-resistant steels [ J ]. Annual Review of Materials Research ,2008,38:471 -503.
  • 2Mukhopadhyay D K, Froes F H, Gelles D S. Development of oxide dispersion strengthened ferritic steels for fusion [ J ]. Journal of Nuclear Materials, 1998,258-263(Part 11):1209-1215.
  • 3吕铮.聚变堆第一壁用纳米结构ODS钢的发展与前瞻[J].原子能科学技术,2011,45(9):1105-1111. 被引量:22
  • 4Pareige P,Miller M K, Stoller R E, et al. Stability of nanometer-sized oxide clusters in mechanically-alloyed steel under ion-induced displacement cascade damage conditions [ J ]. Journal of Nuclear Materlals,2007,360 ( 2 ) : 136 - 142.
  • 5Li M ,Zhou Z J,He P,et al. Annealing behavior of 12-Cr based mechanical alloyed oxide dispersion strengthened ferritic alloy[ J]. Journal of Nuclear Materials,2011,417(1/3) :189 - 192.
  • 6Li M,Zhou Z J,He P, et al. M icrostructure and mechanical property of 12Cr oxide dispersion strengthened ferritic steel for fusion application [ J ]. Fusion Engineering and Design ,2010,85 ( 7/9 ) : 1573 - 1576.
  • 7Miller M K, Hoelzer D T, Kenik E A, et al. Nanometer scale precipitation in ferritic MA/ODS alloy MA957 [ J ]. Journal of Nuclear Materials,2004, 329 -333(part B) :338 -341.
  • 8Miller M K, Russell K F ,Hoelzer D T. Characterization of precipitates in MA/ODS ferritc alloys[ J]. Journal of Nuclear Materials ,2006,351 (1/3) :261 -268.
  • 9吕铮,卢晨阳,张守辉,谢锐,刘春明.纳米结构14Cr-ODS铁素体钢的制备与微观结构[J].金属学报,2012,48(6):649-653. 被引量:13
  • 10Miller M K. Atom Probe Tomography : Analysis at the Atomic Level[ M ]. New York : Kluwer Academic/Plenum Publishers,2000:25.

二级参考文献90

  • 1周邦新.三维原子探针——从探测逐个原子来研究材料的分析仪器[J].自然杂志,2005,27(3):125-129. 被引量:11
  • 2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
  • 3邹俊,黄群英,罗乐,许德政,曾勤,陈明亮,吴宜灿.聚变驱动次临界堆第一壁材料辐照损伤的初步研究[J].核科学与工程,2007,27(2):147-151. 被引量:4
  • 4周邦新,刘文庆.三维原子探针及其在材料科学研究中的应用[J].材料科学与工艺,2007,15(3):405-408. 被引量:15
  • 5LU Z, FAULKNER R G, RIDDLE N, et al. Effect of heat treatment on microstructure and hardness of Eurofer 97, Eurofer ODS and T92 steels[J]. J Nucl Mater, 2009, 386-388.. 445- 448.
  • 6MILLER M K, HOELZER D T, KENIK E A, et al. Nanometer scale precipitation in ferritic MA/ODS alloy MA957[J]. J Nucl Mater, 2004, 329-333 : 338-341.
  • 7YAMASHITA S, AKASAKA N, UKAI S, et al. Microstructural development of a heavily neutron-irradiated ODS ferritie steel (MA957) at elevated temperature [J]. J Nucl Mater, 2007, 367-370 : 202-207.
  • 8KISHIMOTO H, YUTANI K, KASATA R, et al. Heavy-ion irradiation effects on the morphology of complex oxide particles in oxide dispersion strengthened ferritic steels [J]. J Nucl Mater, 2007, 367-370: 179-184.
  • 9TOLOCZKO M B, GELLES D S, GARNER F A, et al. Irradiation creep and swelling from 400 to 600℃ of the oxide dispersion strengthened ferritic alloy MA957 [J]. J Nucl Mater, 2004, 329-333 : 352-355.
  • 10YUTANI K, KISHIMOTO H, KASADA R, et al. Evaluation of Helium effects on swelling behavior of oxide dispersion strengthened ferritic steels under ion irradiation[J]. J Nucl Mater, 2007, 367-370 : 423-427.

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