Advance Search
Volume 44 Issue S1
Jun.  2023
Turn off MathJax
Article Contents
Liu Xiao, Wang Hui, Xiao Jun, Sun Yongduo, Liu Shuaiyang, Zhang Jinyu. Effect of Thermal Aging on Mechanical Properties of Silicon-containing Ferritic/Martensitic Steel[J]. Nuclear Power Engineering, 2023, 44(S1): 147-151. doi: 10.13832/j.jnpe.2023.S1.0147
Citation: Liu Xiao, Wang Hui, Xiao Jun, Sun Yongduo, Liu Shuaiyang, Zhang Jinyu. Effect of Thermal Aging on Mechanical Properties of Silicon-containing Ferritic/Martensitic Steel[J]. Nuclear Power Engineering, 2023, 44(S1): 147-151. doi: 10.13832/j.jnpe.2023.S1.0147

Effect of Thermal Aging on Mechanical Properties of Silicon-containing Ferritic/Martensitic Steel

doi: 10.13832/j.jnpe.2023.S1.0147
  • Received Date: 2022-12-15
  • Rev Recd Date: 2023-03-13
  • Publish Date: 2023-06-15
  • Four kinds of 9Cr- ferritic/martensitic (F/M) steels with different Si contents were heat aged at 550°C (the longest time was 5000 h), and their mechanical properties such as yield strength (Rp0.2), tensile strength (Rm) and elongation (A) were tested. The relationship between microstructure and mechanical properties was studied by means of scanning electron microscope/energy dispersive spectrometer (SEM/EDS) and transmission electron microscope (TEM). The results show that the strength of 9Cr-F/M steel can be improved by adding a small amount of Si, and when the Si content (mass fraction) is 0.7%, Rp0.2 and Rm reach the maximum, but the addition of Si will promote Laves phase precipitation. Aging time (t) has a significant effect on the plasticity of 9Cr-F/M steel. When t < 2500 h, the plasticity of 9Cr-F/M steel has little change, but when the Si content is increased to 1.0%, the plasticity decreases greatly after aging for 5000 h, which is attributed to the precipitation and growth of Laves phase at the grain boundary.

     

  • loading
  • [1]
    李辉,李烁,史春丽,等. 超低碳低活化铁素体/马氏体钢的低温韧性[J]. 金属热处理,2018, 43(1): 22-27. doi: 10.13251/j.issn.0254-6051.2018.01.005
    [2]
    ALLEN T R, KAOUMI D, WHARRY J P, et al. Characterization of microstructure and property evolution in advanced cladding and duct: materials exposed to high dose and elevated temperature[J]. Journal of Materials Research, 2015, 30(9): 1246-1274. doi: 10.1557/jmr.2015.99
    [3]
    KLUEH R L. Ferritic/martensitic steels for advanced nuclear reactors[J]. Transactions of the Indian Institute of Metals, 2009, 62(2): 81-87. doi: 10.1007/s12666-009-0011-3
    [4]
    ZHANG J S. A review of steel corrosion by liquid lead and lead–bismuth[J]. Corrosion Science, 2009, 51(6): 1207-1227. doi: 10.1016/j.corsci.2009.03.013
    [5]
    ZHANG J S, LI N. Review of the studies on fundamental issues in LBE corrosion[J]. Journal of Nuclear Materials, 2008, 373(1-3): 351-377. doi: 10.1016/j.jnucmat.2007.06.019
    [6]
    SCHROER C, TSISAR V, DURAND A, et al. Corrosion in iron and steel T91 caused by flowing lead-bismuth eutectic at 400℃ and 10-7 mass% dissolved oxygen[J]. Journal of Nuclear Engineering and Radiation Science, 2019, 5(1): 011006. doi: 10.1115/1.4040937
    [7]
    WEISENBURGER A, SCHROER C, JIANU A, et al. Long term corrosion on T91 and AISI1 316L steel in flowing lead alloy and corrosion protection barrier development: experiments and models[J]. Journal of Nuclear Materials, 2011, 415(3): 260-269. doi: 10.1016/j.jnucmat.2011.04.028
    [8]
    丁君艳. 9-12%Cr铁素体/马氏体耐热钢的显微组织和力学性能研究[D]. 淄博: 山东理工大学, 2008: 39.
    [9]
    宋亮亮. 含硅9Cr-ODS钢设计与性能研究[D]. 合肥: 中国科学技术大学, 2018: 62-65.
    [10]
    CHEN S H, RONG L J. Effect of silicon on the microstructure and mechanical properties of reduced activation ferritic/martensitic steel[J]. Journal of Nuclear Materials, 2015, 459: 13-19. doi: 10.1016/j.jnucmat.2015.01.004
    [11]
    SAINI N, MULIK R S, MAHAPATRA M M. Study on the effect of ageing on laves phase evolution and their effect on mechanical properties of P92 steel[J]. Materials Science and Engineering:A, 2018, 716: 179-188. doi: 10.1016/j.msea.2018.01.035
    [12]
    BYUN T S, HOELZER D T, KIM J H, et al. A comparative assessment of the fracture toughness behavior of ferritic-martensitic steels and nanostructured ferritic alloys[J]. Journal of Nuclear Materials, 2017, 484: 157-167. doi: 10.1016/j.jnucmat.2016.12.004
    [13]
    ZHAO Y Y, LIANG M T, ZHANG Z Y, et al. Fracture toughness and fracture behavior of CLAM steel in the temperature range of 450℃-550℃[J]. Journal of Nuclear Materials, 2018, 501: 200-207. doi: 10.1016/j.jnucmat.2018.01.039
  • 加载中

Catalog

    通讯作者: 陈斌, bchen63@163.com
    • 1. 

      沈阳化工大学材料科学与工程学院 沈阳 110142

    1. 本站搜索
    2. 百度学术搜索
    3. 万方数据库搜索
    4. CNKI搜索

    Figures(6)  / Tables(1)

    Article Metrics

    Article views (119) PDF downloads(19) Cited by()
    Proportional views
    Related

    /

    DownLoad:  Full-Size Img  PowerPoint
    Return
    Return