Dependence of radiation-induced segregation on dose, temperature and alloy composition in austenitic alloys

Damcott, D. L.; Allen, Todd R.; Was, Gary S.

doi:10.1016/0022-3115(94)00690-3

Cited by 45 publications

(16 citation statements)

References 16 publications

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“…Data for Fe-18Cr-40Ni from this work. [26,27]. and X is the atomic volume, r c the cavity radius, D i,v the interstitial (i) or vacancy (v) diffusion coefficient, K 0 the displacement rate, q d the dislocation density, Z the point defect bias for interstitials (i) or vacancies (v) at dislocations (d) or cavities (c).…”

Section: Influence Of Materials and Radiation Parameters On Swellingmentioning

confidence: 99%

Swelling and radiation-induced segregation in austentic alloys

Allen

Cole

Gan

et al. 2005

Journal of Nuclear Materials

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Section: Influence Of Materials and Radiation Parameters On Swellingmentioning

confidence: 99%

Swelling and radiation-induced segregation in austentic alloys

Allen

Cole

Gan

et al. 2005

Journal of Nuclear Materials

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“…The net result is an accumulation or a depletion of elements at these defect sinks, which can have deleterious effects on polycrystal properties. There have been a number of experimental studies to characterize and understand the mechanisms of radiation-induced segregation in a number of irradiated metal systems [3][4][5][6][7][8][9][10][11][12][13] as well as computational models. Interestingly, these models have to consider both the evolution of defect and defect clusters as well as their destinations.…”

Section: Introductionmentioning

confidence: 99%

Probing grain boundary sink strength at the nanoscale: Energetics and length scales of vacancy and interstitial absorption by grain boundaries inα-Fe

et al. 2012

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The energetics and length scales associated with the interaction between point defects (vacancies and self-interstitial atoms) and grain boundaries in BCC Fe was explored. Molecular statics simulations were used to generate a grain boundary structure database that contained ≈ 170 grain boundaries with varying tilt and twist character. Then, vacancy and self-interstitial atom formation energies were calculated at all potential grain boundary sites within 15Å of the boundary. The present results provide detailed information about the interaction energies of vacancies and selfinterstitial atoms with symmetric tilt grain boundaries in iron and the length scales involved with absorption of these point defects by grain boundaries. Both low and high angle grain boundaries were effective sinks for point defects, with a few low-Σ grain boundaries (e.g., the Σ3{112} twin boundary) that have properties different from the rest. The formation energies depend on both the local atomic structure and the distance from the boundary center. Additionally, the effect of grain boundary energy, disorientation angle, and Σ-designation on the boundary sink strength was explored; the strongest correlation occurred between the grain boundary energy and the mean point defect formation energies. Based on point defect binding energies, interstitials have ≈ 80% more grain boundary sites per area and ≈ 300% greater site strength than vacancies. Last, the absorption length scale of point defects by grain boundaries is over a full lattice unit larger for interstitials than for vacancies (mean of 6-7Å vs. 10-11Å for vacancies and interstitials, respectively).

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“…The largest set of RIS data for iron-chromium-nickel alloys has been generated using proton irradiations [10,11,[15][16][17][18][19][20][21][22] different doses (O.1, 0.3, 0.5, 1.0, and 3.0 dpa). Grain boundary compositions were measured using" both Auger electron spectroscopy (AES) and scanning transmission electron microscopy with energy dispersive x-ray spectroscopy (STEMIEDS), resulting in over 1100 grain boundary composition measurements.…”

Section: -Smentioning

confidence: 99%

The Correlation Between Swelling and Radiation-Induced Segregation in Iron-Chromium-Nickel Alloys

Allen

Busby

Gan

et al. 2000

Effects of Radiation on Materials: 19th International Symposium

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The magnitudes of both void swelling and radiation-induced segregation (RIS) in austenitic iron-chromium-nickel alloys are dependent on bulk alloy composition. In this work, the resistance to swelling from major element segregation is estimated and alloys with greater nickel enrichment and fast-developing segregation profiles are shown to be less prone to swelling. In austenitic iron-chromium-nickel alloys, the total swelling depends on the duration of the transient swelling period that precedes steady-state swelling. A longer transient swelling period leads to less overall swelling for the same irradiation dose. The duration of this transient period depends on the void nucleation rate which is determined directly by the average vacancy diffusivity and indirectly by the magnitude of the segregation to the void surface. Alloys with faster vacancy diffusion have a slower void nucleation rate, a longer transient swelling period, and less swelling. Radiation-induced segregation affects swelling by decreasing the vacancy flux to the void. Because the diffusivity of nickel via the vacancy flux is slow relative to chromium, nickel enriches and chromium depletes at void surfaces during irradiation in all austenitic iron-chromium-nickel alloys. This local composition change reduces the subsequent vacancy flux to the voids, increasing the bulk point defect recombination rate, reducing the bulk vacancy concentration, which further reduces the nucleation rate and swelling. Alloys that display the greatest amount of nickel enrichment and chromium depletion are found to be most resistant to void swelling, as predicted from both void nucleation and void growth considerations.

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Dependence of radiation-induced segregation on dose, temperature and alloy composition in austenitic alloys

Cited by 45 publications

References 16 publications

Swelling and radiation-induced segregation in austentic alloys

Swelling and radiation-induced segregation in austentic alloys

Probing grain boundary sink strength at the nanoscale: Energetics and length scales of vacancy and interstitial absorption by grain boundaries inα-Fe

The Correlation Between Swelling and Radiation-Induced Segregation in Iron-Chromium-Nickel Alloys

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