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Communication Dans Un Congrès Année : 2013

Influence of strain localization on IASCC of proton irradiated 304L stainless steel in simulated PWR primary water

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Morgane Le Millier
  • Fonction : Auteur
  • PersonId : 762644
  • IdRef : 184963478
Olivier Calonne
  • Fonction : Auteur
Jérôme Crépin
Cecilie Duhamel
Lionel Fournier
  • Fonction : Auteur
Fabrice Gaslain
Eva Héripré
Ovidiu Toader
  • Fonction : Auteur
Yoann Vidalenc
  • Fonction : Auteur
Gary Was
  • Fonction : Auteur

Résumé

Crack initiation has been correlated to crystallographic orientations and strain field measurements using SEM digital image correlation technique coupled with EBSD cartography in order to gain insight into the influence of strain localization on IASCC of proton-irradiated 304L stainless steel in simulated primary water. Type 304L specimens were irradiated with 2 MeV protons at 360°C to 5 and 10 dpa and subsequently strained in simulated primary water under monotonic and pseudo-cyclic loadings. Intergranular cracks occurring on random high angle boundaries nearly perpendicular to the tensile axis were observed. Cracking features differences between monotonic and pseudo-cyclic tests are discussed. Increasing the macroscopic strain for monotonic loading results in a higher density of cracks but does not change the crack length whereas the increase of strain for pseudo-cyclic test induces an important increase of the cracks propagation. Strain field analysis shows a strong heterogeneity, with localization in narrow lines and near some grain boundaries in the irradiated areas. On the contrary, no localization in narrow lines is observed for the non-irradiated material.
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Dates et versions

hal-00999080 , version 1 (03-06-2014)

Identifiants

  • HAL Id : hal-00999080 , version 1

Citer

Morgane Le Millier, Olivier Calonne, Jérôme Crépin, Cecilie Duhamel, Lionel Fournier, et al.. Influence of strain localization on IASCC of proton irradiated 304L stainless steel in simulated PWR primary water. 6th international conference on environmental degradation of materials in nuclear power systems - water reactors, Aug 2013, Asheville, United States. 16 p. ⟨hal-00999080⟩
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