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Using fast reactor component evaluation for pressurized water reactor life extension

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  • Nuclear Reactor Life Extension
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Abstract

An understanding of the effects of long-term, low-dose-rate radiation on core components is critical to light-water reactor plant life extension. Following reactor shutdown, materials that had experienced long exposures to low-dose-rate irradiation were retrieved from the EBR-II research reactor for analysis. These components are being analyzed to provide insight into pressurized water reactor life extension. In this work, three examples of EBR-II materials analyses are highlighted: radiation-induced segregation in 304 stainless steel, stress relaxation in Inconel X750, and swelling in 316 stainless steel.

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Authors and Affiliations

  1. Argonne National Laboratory-West, USA

    T. R. Allen & J. I. Cole

  2. Oak Ridge National Laboratory, USA

    E. A. Kenik

  3. Argonne National Laboratory, USA

    H. Tsai

  4. Japan Nuclear Cycle Development Institute, Japan

    S. Ukai, S. Mizuta & T. Yoshitake

Authors
  1. T. R. Allen
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  2. J. I. Cole
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  3. E. A. Kenik
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  4. H. Tsai
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  5. S. Ukai
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  6. S. Mizuta
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  7. T. Yoshitake
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Additional information

For more information, contact T.R. Allen, Argonne National Laboratory-West, P.O. Box 2528, Idaho Falls, Idaho 83403-2528;(208)533-7760; fax (208) 533-7863; e-mail todd.allen@anlw.anl.gov.

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Allen, T.R., Cole, J.I., Kenik, E.A. et al. Using fast reactor component evaluation for pressurized water reactor life extension. JOM 51, 27–30 (1999). https://doi.org/10.1007/s11837-999-0183-7

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  • DOI: https://doi.org/10.1007/s11837-999-0183-7

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