Skip to main content

Part of the book series: The Minerals, Metals & Materials Series ((MMMS))

Abstract

Thermal degradation of cast stainless steels was studied to provide an extensive knowledgebase for the assessment of structural integrity during extended operations of reactor coolant systems. The CF3 and CF8 series cast stainless steels with relatively low (5–12%) δ-ferrite contents were thermally aged at 290–400 °C for up to 10,000 h and tested to measure changes in tensile and impact properties. The aging treatments caused significant reduction of tensile ductility, but only slight softening or negligible strength change. The thermal aging also caused significant reduction of upper shelf energy and large shift of ductile-brittle transition temperature (ΔDBTT). The most influential factor in thermal degradation was ferrite content because of the major degradation mechanism occurring in the phase, while the nitrogen and carbon contents caused only weak effects. An integrated model is being developed to correlate the mechanical property changes with microstructural and compositional parameters.

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

Access this chapter

Chapter
USD 29.95
Price excludes VAT (USA)
  • Available as PDF
  • Read on any device
  • Instant download
  • Own it forever
eBook
USD 259.00
Price excludes VAT (USA)
  • Available as EPUB and PDF
  • Read on any device
  • Instant download
  • Own it forever
Hardcover Book
USD 329.99
Price excludes VAT (USA)
  • Durable hardcover edition
  • Dispatched in 3 to 5 business days
  • Free shipping worldwide - see info

Tax calculation will be finalised at checkout

Purchases are for personal use only

Institutional subscriptions

References

  1. J.T. Busby, P.G. Oberson, C.E. Carpenter, M. Srinivasan, Expanded Materials Degradation Assessment (EMDA)-Vol. 2: Aging of Core Internals and Piping Systems, NUREG/CR-7153, Vol. 2, ORNL/TM-2013/532, October 2014

    Google Scholar 

  2. R. Dyle, Materials Degradation Matrix and Issue Management Tables Overview-LTO Update (The 2nd Workshop on U.S. Nuclear Power Plant Life Extension, Washington, D.C, 2011)

    Google Scholar 

  3. O.K. Chopra, A. Sather, Initial Assessment of the Mechanisms and Significance of Low-T Embrittlement of Cast Stainless Steels in LWR Systems (NUREG/CR–5385, 1990)

    Google Scholar 

  4. O.K. Chopra, Effects of Thermal Aging and Neutron Irradiation on Crack Growth Rate and Fracture Toughness of Cast Stainless Steels and Austenitic Stainless Steel Welds (NUREG/CR-7185, 2014)

    Google Scholar 

  5. O.K. Chopra, Estimation of Fracture Toughness of Cast Stainless Steels during Thermal Aging in LWR Systems (NUREG/CR-4513, 1991)

    Google Scholar 

  6. W.F. Michaud, P.T. Toben, W.K. Soppet, O.K. Chopra, Tensile-Property Characterization of Thermally Aged Cast Stainless Steels (NUREG/CR-6142, 1994)

    Google Scholar 

  7. H.M. Chung, T.R. Leax, Mater. Sci. Technol. 6, 249–262 (1990)

    Article  CAS  Google Scholar 

  8. H.M. Chung, Evaluation of Aging of Cast Stainless Steel Components (Presented at ASME Pressure Vessel & Piping Conference, San Diego, CA, 1991)

    Google Scholar 

  9. H.M. Chung, Presented at the American Society for Mechanical Engineers-Material Properties Council Symposium on Plant Life Extension for Nuclear Components (Honolulu, Hawaii, 1989)

    Google Scholar 

  10. T.S. Byun, Y. Yang, N.R. Overman, J.T. Busby, Thermal aging phenomena in cast duplex stainless steels. JOM 68(2), 507–526 (2016)

    Article  CAS  Google Scholar 

  11. M. Murayama, Y. Katayama, K. Hono, Metall. Mater. Trans. A 30A, 345 (1999)

    Article  CAS  Google Scholar 

  12. T. Sourmail, Mater. Sci. Tech. 17, 1 (2001)

    Google Scholar 

  13. L.P. Stoter, J. Mater. Sci. 16, 1039 (1981)

    Google Scholar 

  14. B. Weiss, R. Stickler, Metal Trans. 3, 851 (1972)

    Google Scholar 

  15. J.E. Spruiell, J.A. Scott, C.S. Ary, R.L. Hardin, Metal Trans. 4, 1533 (1973)

    Google Scholar 

  16. T.S. Byun, N.R. Overman, T.G. Lach, Mechanical Properties of Model Cast Austenitic Stainless Steels after Thermal Aging for 1500 h, LWRS Report, PNNL-25377, April 2016

    Google Scholar 

  17. T.G. Lach, T.S. Byun, Microstructural Evolution of Cast Austenitic Stainless Steels under Accelerated Thermal Aging, 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors, Portland, Oregon, USA, Aug 13–17, 2017

    Google Scholar 

  18. W. Oldfield, Curve fitting impact test data: a statistical procedure. ASTM Standardization News 3(11), 24–29 (1975)

    Google Scholar 

  19. K. Yeager, Nonlinear curve fitting and the Charpy impact test: statistical, mathematical, and physical considerations (https://www.uakron.edu/dotAsset/2116623.pdf)

  20. T.S. Byun, N. Hashimoto, K. Farrell, Acta Mater. 52, 3889–3899 (2004)

    Google Scholar 

Download references

Acknowledgements

This research was sponsored by U.S. Department of Energy/Office of Nuclear Energy through Light Water Reactor Sustainability R&D Program and International Nuclear Energy Research Initiative (I-NERI) Program. Pacific Northwest National Laboratory is operated by Battelle Memorial Institute for the U.S. Department of Energy under Contract No. DEAC05-76RL01830.

Author information

Authors and Affiliations

Authors

Corresponding author

Correspondence to Thak Sang Byun .

Editor information

Editors and Affiliations

Rights and permissions

Reprints and permissions

Copyright information

© 2019 The Minerals, Metals & Materials Society

About this paper

Cite this paper

Byun, T.S., Lach, T.G., Yang, Y., Jang, C. (2019). Influence of δ-Ferrite Content on Thermal Aging Induced Mechanical Property Degradation in Cast Stainless Steels. In: Jackson, J., Paraventi, D., Wright, M. (eds) Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors. The Minerals, Metals & Materials Series. Springer, Cham. https://doi.org/10.1007/978-3-030-04639-2_123

Download citation

Publish with us

Policies and ethics