Skip to main content
Log in

Mechanical property and irradiation damage of China Low Activation Martensitic (CLAM) steel

  • Article
  • Published:
Science China Physics, Mechanics and Astronomy Aims and scope Submit manuscript

Abstract

China Low Activation Martensitic (CLAM) steel is being studied to develop the structural materials for a fusion reactor, which has been designed based on the well-known 9Cr1.5WVTa steel. The effect of tempering temperature on hardness and microstructure of CLAM steel was studied. The strength of CLAM steel increased by adding silicon, and the ductility remained constant. Conversely, while CLAM steel maintained good ductility with the addition of yttrium, its tensile strengths were greatly degraded. Behaviors under electron irradiation of CLAM steel were examined using the high voltage electron microscope. Electron irradiation at 450°C formed many voids in CLAM steel with basic composition, whereas CLAM with silicon steel did not change the microstructure significantly.

This is a preview of subscription content, log in via an institution to check access.

Access this article

Price excludes VAT (USA)
Tax calculation will be finalised during checkout.

Instant access to the full article PDF.

Similar content being viewed by others

References

  1. Muroga T, Gasparotto, Zinkle S J. Overview of materials research for fusion reactors. Fusion Eng Design, 2002, 61–62: 13–25

    Article  Google Scholar 

  2. Victoria M, Gavillet D, Sptitig P, et al. Microstructure and mechanical properties of newly developed low activation martensitic steels. J Nucl Mater, 1996, 233-237: 326–330

    Article  ADS  Google Scholar 

  3. Fernández P, Lancha A M, Lapeña J, et al. Metallurgical characterization of the reduced activation ferritic/martensitic steel Eurofer’97 on as-received condition. Fusion Eng Design, 2001, 58–59: 787–792

    Article  Google Scholar 

  4. Klueh R L, Gelles D S, Jitsukawa S, et al. Ferritic/martensitic steels—overview of recent results. J Nucl Mater, 2002, 307–311: 455–465

    Article  Google Scholar 

  5. Song Y, Chen Q, Wu Y, et al. A study of effect of yttrium in low-alloy martensitic cast steel (in Chinese). Mater Mech Eng, 1994, 18: 35–35

    Google Scholar 

  6. Pan F, Ding P, Zhou S, et al. Effects of silicon additions on the mechanical properties and microstructure of high speed steels. Acta Mater, 1997, 45: 4703–3712

    Article  Google Scholar 

  7. Faulkner R G, Song S, Flewitt P E J. Irradiation-induced silicon segregation in ferritic steels. J Nucl Mater, 1994, 212–215: 608–611

    Article  Google Scholar 

  8. Nikolaeva A V, Nikolaev Y A, Kryukov A M. The contribution of grain boundary effects to low-alloy steel irradiation embrittlement. J Nucl Mater, 1994, 218: 85–93

    Article  ADS  Google Scholar 

  9. Zhang Q, Yang J. Microstructure and properties of bainite-martensite steel plate (in Chinese). Heat Treat Metals, 2004, 29: 46–48

    Google Scholar 

  10. Muroga T, Yoshida N, Kitajima K. EDS investigation of solute-precipitate interactions in ferritic steels under irradiation. Ultramicroscopy, 1987, 22: 281–288

    Article  Google Scholar 

Download references

Author information

Authors and Affiliations

Authors

Corresponding author

Correspondence to FaRong Wan.

Rights and permissions

Reprints and permissions

About this article

Cite this article

Zhu, Y., Wan, F., Gao, J. et al. Mechanical property and irradiation damage of China Low Activation Martensitic (CLAM) steel. Sci. China Phys. Mech. Astron. 55, 2057–2061 (2012). https://doi.org/10.1007/s11433-012-4865-8

Download citation

  • Received:

  • Accepted:

  • Published:

  • Issue Date:

  • DOI: https://doi.org/10.1007/s11433-012-4865-8

Keywords

Navigation