Application of a three-feature dispersed-barrier hardening model to neutron-irradiated Fe–Cr model alloys

Bergner, F.; Pareige, C.; Hernández‐Mayoral, M.; Malerba, Lorenzo; Heintze, C.

doi:10.1016/j.jnucmat.2014.01.024

Cited by 127 publications

(51 citation statements)

References 17 publications

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“…Finally, it concludes that, since Cr-rich α' precipitation is sensitive to initial Cr composition [13,16,17], the composition-dependent hardening response at these conditions could be attributed to the Cr-rich α' phase. Similar composition dependencies based on the α' precipitation response under irradiation have been suggested by other studies of FeCr alloys irradiated to similar low dose (<5 dpa) LWR relevant conditions [26][27][28]. Although microstructural information in the high dose irradiated specimens is unavailable, and hence conclusive factors for the lack of a composition-dependent hardening response at higher doses remains undetermined, it is possible some details could be inferred from FeCr alloys as they show similar mechanical performance across the same dose and temperature regime.…”

Section: Discussionsupporting

confidence: 85%

Mechanical properties of neutron-irradiated model and commercial FeCrAl alloys

Field

Briggs

Sridharan

et al. 2017

Journal of Nuclear Materials

125

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The development and understanding of the mechanical properties of neutron-irradiated FeCrAl alloys is increasingly a critical need as these alloys continue to become more mature for nuclear reactor applications. This study focuses on the mechanical properties of model FeCrAl alloys and of a commercial FeCrAl alloy neutron-irradiated to up to 13.8 displacements per atom (dpa) at irradiation temperatures between 320 and 382°C. Tensile tests were completed at room temperature and at 320°C, and a subset of fractured tensile specimens was examined by scanning electron microscopy. Results showed typical radiation hardening and embrittlement indicative of high chromium ferritic alloys with strong chromium composition dependencies at lower doses. At and above 7.0 dpa, the mechanical properties saturated for both the commercial and model FeCrAl alloys, although brittle cleavage fracture was observed at the highest dose in the model FeCrAl alloy with the highest chromium content (18 wt %). The results suggest the composition and microstructure of FeCrAl alloys plays a critical role in the mechanical response of FeCrAl alloys irradiated near temperatures relevant to light water reactors.

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Section: Discussionsupporting

confidence: 85%

Mechanical properties of neutron-irradiated model and commercial FeCrAl alloys

Field

Briggs

Sridharan

et al. 2017

Journal of Nuclear Materials

125

View full text Add to dashboard Cite

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“…[1]) for solid solution and dispersed oxide hardening in a Cu-Au alloy. [24] In a more complex case with a greater number of obstacle types, Bergner et al [40] examined the capabilities of the DBH and BKS models in combination with several superposition principles in an Fe-Cr model alloy. The hardening parameter a was calculated for a 0 phase particles, dislocation loops, and NiSiPCrrich clusters in an Fe-Cr model alloy.…”

Section: ½4mentioning

confidence: 99%

“…Experimental studies [40,53] have used mean defect size as an input to hardening models such as DBH and BKS; however, the validity of such an approach has never been shown. Any significant change in hardening as a function of distribution standard deviation would invalidate such an approach for a symmetric distribution of defects.…”

Section: Size and Spatial Distribution Of Voidsmentioning

confidence: 99%

Analysis of Obstacle Hardening Models Using Dislocation Dynamics: Application to Irradiation-Induced Defects

Sobie

Bertin

Capolungo

2015

Metall Mater Trans A

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Irradiation hardening in a-iron represents a critical factor in nuclear reactor design and lifetime prediction. The dispersed barrier hardening, Friedel Kroupa Hirsch (FKH), and Bacon Kocks Scattergood (BKS) models have been proposed to predict hardening caused by dislocation obstacles in metals, but the limits of their applicability have never been investigated for varying defect types, sizes, and densities. In this work, dislocation dynamics calculations of irradiationinduced obstacle hardening in the athermal case were compared to these models for voids, selfinterstitial atom (SIA) loops, and a combination of the two types. The BKS model was found to accurately predict hardening due to voids, whereas the FKH model was superior for SIA loops. For both loops and voids, the hardening from a normal distribution of defects was compared to that from the mean size, and was shown to have no statistically significant dependence on the distribution. A mean size approach was also shown to be valid for an asymmetric distribution of voids. A non-linear superposition principle was shown to predict the hardening from the simultaneous presence of voids and SIA loops.

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“…For a longer-term application, effort has been put to develop fully physically informed suites of computer simulation codes, aimed at predicting RPV steel radiation hardening [8,9], including microstructural examination studies in support of modelling [10][11][12][13][14][15][16][17][18][19][20][21][22][23][24][25][26][27][28]. These studies revealed that radiation hardening in RPV steels, as well as in other types of iron alloys such as high-Cr ferritic-martensitic (F-M) materials, is mainly the consequence of the formation of high densities (~10 23 m -3 ) of nanometre-size solute-rich clusters (NSRC), which act as obstacles to dislocation motion [29,30]. Importantly, NSRC are also found in steels containing low quantities of Cu for which all solute species are found below their solubility limit.…”

Section: Introductionmentioning

confidence: 99%

The Dominating Mechanisms for the Formation of Solute-Rich Clusters in Steels under Irradiation

et al. 2019

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The formation of nano-sized, coherent, solute-rich clusters (NSRC) is known to be an important factor degrading the macroscopic properties of steels under irradiation. The mechanisms driving their formation are still debated. This work focuses on low-Cu reactor pressure vessel (RPV) steels, where solute species are generally not expected to precipitate. We rationalize the processes taking place at the nanometre scale under irradiation, relying on the latest theoretical and experimental evidence on atomic-level diffusion and transport processes. These are compiled in a new model, based on the object kinetic Monte Carlo (OKMC) technique. We evaluate the relevance of the underlying physical assumptions by applying the model to a large variety of irradiation experiments. Our model predictions are compared with new experimental data obtained with atom probe tomography and small angle neutron scattering, complemented with information from the literature. The results of this study reveal that the role of immobilized selfinterstitial atoms (SIA) loops dominates the nucleation process of NSRC.

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Application of a three-feature dispersed-barrier hardening model to neutron-irradiated Fe–Cr model alloys

Cited by 127 publications

References 17 publications

Mechanical properties of neutron-irradiated model and commercial FeCrAl alloys

Mechanical properties of neutron-irradiated model and commercial FeCrAl alloys

Analysis of Obstacle Hardening Models Using Dislocation Dynamics: Application to Irradiation-Induced Defects

The Dominating Mechanisms for the Formation of Solute-Rich Clusters in Steels under Irradiation

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