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Irradiation Creep and Irradiation Stress Relaxation of 316 and 304L Stainless Steels in Thermal and Fast Neutron Spectrum Reactors

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Proceedings of the 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems — Water Reactors

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Abstract

Irradiation creep and irradiation stress relaxation data have been obtained for CW 316 SS and SA 304L SS in the Halden reactor. The measurements were performed on-line during irradiation. The irradiation creep in this thermal neutron spectrum reactor was observed to be very different than values measured in fast neutron spectrum reactors. The steady state irradiation creep rate was higher in this and other thermal neutron spectrum reactors than in fast neutron spectrum reactors. On the other hand, the transient irradiation creep component was lower in thermal neutron spectrum reactors than fast neutron spectrum reactors. Therefore, fast reactor irradiation creep data are not recommended for application to light water reactors.

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References

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Author information

Authors and Affiliations

  1. Westinghouse Electric Company, 5801 Bluff Road, Columbia, SC, 29250, USA

    John Paul Foster

  2. OECD Halden Reactor Project, Halden, Norway

    Torill M. Karlsen

Authors
  1. John Paul Foster
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  2. Torill M. Karlsen
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Editor information

Editors and Affiliations

  1. Oak Ridge National Laboratory, USA

    Jeremy T. Busby

  2. Electric Power Research Institute, USA

    Gabriel Ilevbare

  3. GE Global Research Center, USA

    Peter L. Andresen

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© 2011 TMS (The Minerals, Metals & Materials Society)

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Foster, J.P., Karlsen, T.M. (2011). Irradiation Creep and Irradiation Stress Relaxation of 316 and 304L Stainless Steels in Thermal and Fast Neutron Spectrum Reactors. In: Busby, J.T., Ilevbare, G., Andresen, P.L. (eds) Proceedings of the 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems — Water Reactors. Springer, Cham. https://doi.org/10.1007/978-3-319-48760-1_82

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