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In Situ and Ex Situ Observations of the Influence of Twin Boundaries on Heavy Ion Irradiation Damage Effects in 316L Austenitic Stainless Steels

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Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors

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

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References

  1. X.M. Bai et al., Efficient annealing of radiation damage near grain boundaries via interstitial emission. Science 327(5973), 1631–1634 (2010)

    Article  CAS  Google Scholar 

  2. M.J. Demkowicz, O. Anderoglu, X.H. Zhang, A. Misra, The influence of sigma 3 twin boundaries on the formation of radiation-induced defect clusters in nanotwinned Cu. J. Mater. Res. 26(14), 1666–1675 (2011)

    Article  CAS  Google Scholar 

  3. W.Z. Han et al., Effect of grain boundary character on sink efficiency. Acta Mater. 60(18), 6341–6351 (2012)

    Article  CAS  Google Scholar 

  4. G.G. Lee, H.H. Jin, Y.B. Lee, J. Kwon, Observation and rate theory modeling of grain boundary segregation in Σ3 twin boundaries in ion-irradiated stainless steel 316. J. Nucl. Mater. 449(1–3), 234–241 (2014)

    Article  CAS  Google Scholar 

  5. C.M. Barr et al., Anisotropic radiation-induced segregation in 316L austenitic stainless steel with grain boundary character. Acta Mater. 67, 145–155 (2014). doi:https://doi.org/10.1016/j.actamat.2013.11.060

    Article  CAS  Google Scholar 

  6. J. Li et al., In situ study of defect migration kinetics and self-healing of twin boundaries in heavy ion irradiated nanotwinned metals. Nano Lett. 15(5), 2922–2927 (2015)

    Article  CAS  Google Scholar 

  7. P.L. Lane, P.J. Goodhew, Dislocation loops at twin boundaries in an ion-irradiated austenitic alloy. Philos. Mag. A 46(4), 597–606 (1982)

    Article  CAS  Google Scholar 

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Authors and Affiliations

  1. Department of Nuclear Engineering, University of Wisconsin, Madison, USA

    G. Meric de Bellefon & K. Sridharan

  2. Unité Matériaux et Transformation (UMET), CNRS, Université de Lille 1, Villeneuve-d’Ascq, France

    J. C. van Duysen

  3. Department of Nuclear Engineering, University of Tennessee, Knoxville, USA

    J. C. van Duysen

  4. EDF—Centre de Recherche des Renardieres, Moret sur Loing, France

    J. C. van Duysen

Authors
  1. G. Meric de Bellefon
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  2. J. C. van Duysen
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  3. K. Sridharan
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Corresponding author

Correspondence to G. Meric de Bellefon .

Editor information

Editors and Affiliations

  1. Idaho National Laboratory, Idaho Falls, ID, USA

    John H. Jackson

  2. Naval Nuclear Laboratory, Pittsburgh, PA, USA

    Denise Paraventi

  3. Chalk River Laboratories, Canadian Nuclear Laboratories, Chalk River, ON, Canada

    Michael Wright

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© 2019 The Minerals, Metals & Materials Society

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de Bellefon, G.M., van Duysen, J.C., Sridharan, K. (2019). In Situ and Ex Situ Observations of the Influence of Twin Boundaries on Heavy Ion Irradiation Damage Effects in 316L Austenitic 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_37

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