Skip to main content
SpringerLink
Log in

Effect of Heat Treatment Process on Mechanical Properties and Microstructure of Modified CNS- II F/M Steel

  • Published:
Journal of Iron and Steel Research International Aims and scope Submit manuscript

Abstract

Ferritic/martensitic (F/M) steels have been recommended as one of the candidate materials for supercritical water cooled reactor (SCWR) in-core components use for its high thermal conductivity, low thermal expansion coefficient and inherently good dimensional stability under irradiation condition in comparison to austenitic steel. CNS- II F/M steel which has good mechanical properties was one of the 9–12Cr F/M steels designed for SCWR in the previous work. In this study a modified CNS- II F/M steel was used and it’s ultimate tensile strength was 925 MPa at room temperature and 483 MPa at 600 °C after optimizing heat treatment parameter. The ductile to brittle transition temperature of modified CNS-II F/M steel is —55 °C. Those are at the same level or even higher than that of CNS-II and some commercial F/M steels nominated for SCWR in-core component use. The transmission electron microscope (TEM) results showed that the mechanical properties of the tempered martensite was closely related to the decomposition stage of the martensite.

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

Access this article

Log in via an institution

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

Instant access to the full article PDF.

Institutional subscriptions

Similar content being viewed by others

References

  1. Abram T, Ion S. Generation-IV Nuclear Power: A Review of the State of the Science [J]. Energy Policy, 2008, 36(12): 4323.

    Article  Google Scholar 

  2. Murty K L, Chrtit I. Structural Materials for Gen-IV Nuclear Reactors: Challenges and Opportunities [J]. Journal of Nuclear Materials, 2008, 383(1/2): 189.

    Article  Google Scholar 

  3. Yvon P, Carré F. Structural Materials Challenges for Advanced Reactor Systems [J]. Journal of Nuclear Materials, 2009, 385(2): 217.

    Article  Google Scholar 

  4. Klueh R L. Reduced-Activation Steels: Future Development for Improved Creep Strength [J]. Journal of Nuclear Materials, 2009, 375(2): 159.

    Article  Google Scholar 

  5. Ghassemi-Armaki H, Chen R P, Maruyama K et al. Static Recovery of Tempered Lath Martensite Microstructures During Long-Term Aging in 9-12%Cr Heat Resistant Steels [J]. Materials Letters, 2009, 63(28): 2423.

    Article  Google Scholar 

  6. Schneider A, Inden G. Simulation of the Kinetics of Precipitation Reactions in Ferritic Steels [J]. Acta Materialia, 2005, 53(2): 519.

    Article  Google Scholar 

  7. Lindau R, Möslang A, Schirra M. Thermal and Mechanical Behavior of the Reduced-Activation-Ferritic-Martensitic Steel EUROFER [J]. Fusion Engineering and Design, 2002, 61–62(12), 659.

    Article  Google Scholar 

  8. Tong Z, Dai Y. The Microstructure and Tensile Properties of Ferritic/Martensitic Steels T91, EUROFER-97 AND F82H Irradiated up to 20dpa in STIP-II [J]. Journal of Nuclear Materials, 2010, 398(1/2/3): 43.

    Article  Google Scholar 

  9. Maloy Stuart A, Romero T, James M R et al. Tensile Testing of EP-823 and HT-9 After Irradiation in STIP II [J]. Journal of Nuclear Materials, 2006, 3561/2/3): 56.

    Article  Google Scholar 

  10. Maloy Stuart A, Romero T, James M R et al. Embrittlement of Irradiated Ferritic/Martensitic Steels in the Absence of Irradiation Hardening [J]. Journal of Nuclear Materials, 2008, 377(3): 427.

    Article  Google Scholar 

  11. Rieth M, Dafferner B, Röhrig H-D. Embrittlement behavior of Different International Low Activation Alloys After Neutron Irradiation [J]. Journal of Nuclear Materials, 1998, 258–263: 1147.

    Article  Google Scholar 

  12. Klueh R L, Soolov M A, Hashimoto N. Mechanical Properties of Unirradiated and Irradiated Reduced-Activation Martensitic Steels With and Without Nickel Compared to Properties of Commercial Steels [J], Journal of Nuclear Materials, 2008, 374(1/2): 220.

    Article  Google Scholar 

  13. Dai Y, Marmy P. Charpy Impact Tests on Martensitic/Ferritic Steels After Irradiation in SINQ Target-3 [J]. Journal of Nuclear Materials, 2005, 343(1/2/3): 247.

    Article  Google Scholar 

  14. Pešiĉka J, Kuzě I R, Dronhofer A, et al. The Evolution of Dislocation Density During Heat Treatment and Creep of Tempered Martensite Ferritic Steels [J]. Acta Materialia, 2003, 51(16): 4847.

    Article  Google Scholar 

Download references

Author information

Authors and Affiliations

  1. School of Materials Science and Engineering, University of Science and Technology Beijing, Beijing, 100083, China

    Ying Yang (Doctor Candidate), Qing-zhi Yan, Rong Ma & Chang-chun Ge

Authors
  1. Ying Yang
    View author publications

    You can also search for this author in PubMed Google Scholar

  2. Qing-zhi Yan
    View author publications

    You can also search for this author in PubMed Google Scholar

  3. Rong Ma
    View author publications

    You can also search for this author in PubMed Google Scholar

  4. Chang-chun Ge
    View author publications

    You can also search for this author in PubMed Google Scholar

Corresponding author

Correspondence to Ying Yang.

Additional information

Foundation Item: Item Sponsored by National Basic Research Program of China (2007CB209800)

Rights and permissions

Reprints and permissions

About this article

Cite this article

Yang, Y., Yan, Qz., Ma, R. et al. Effect of Heat Treatment Process on Mechanical Properties and Microstructure of Modified CNS- II F/M Steel. J. Iron Steel Res. Int. 18, 65–70 (2011). https://doi.org/10.1016/S1006-706X(12)60011-9

Download citation

  • Received:

  • Published:

  • Issue Date:

  • DOI: https://doi.org/10.1016/S1006-706X(12)60011-9

Key words

Search

Navigation