Recent advances in the understanding of damage production and its consequences on void swelling, irradiation creep and growth

Woo, C.H.; Singh, B.N.; Семенов, А.А.

doi:10.1016/s0022-3115(96)00482-5

Cited by 41 publications

(15 citation statements)

References 72 publications

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“…4,5 Under cascade damage irradiation, however, point defects are produced in the form of small mobile or immobile vacancy and interstitial clusters. [8][9][10][11][12] Recognition of this fact has led to the introduction of production bias 13,14 as an alternative driving force for the microstructure evolution at elevated temperatures. An additional effect of cascade damage is the fluctuations in the point-defect fluxes received by the void embryos, caused by the random ͑in time and space͒ production of point defects in packets during cascade irradiation.…”

Section: Introductionmentioning

confidence: 99%

Void nucleation at elevated temperatures under cascade-damage irradiation

Семенов

Woo

2002

Phys. Rev. B

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The effects on void nucleation of fluctuations respectively due to the randomness of point-defect migratory jumps, the random generation of free point defects in discrete packages, and the fluctuating rate of vacancy emission from voids are considered. It was found that effects of the cascade-induced fluctuations are significant only at sufficiently high total sink strength. At lower sink strengths and elevated temperatures, the fluctuation in the rate of vacancy emission is the dominant factor. Application of the present theory to the void nucleation in annealed pure copper neutron-irradiated at elevated temperatures with doses of 10 Ϫ4 -10 Ϫ2 NRT dpa showed reasonable agreement between theory and experiment. This application also predicts correctly the temporal development of large-scale spatial heterogeneous microstructure during the void nucleation stage.Comparison between calculated and experimental void nucleation rates in neutron-irradiated molybdenum at temperatures where vacancy emission from voids is negligible showed reasonable agreement as well. It was clearly demonstrated that the athermal shrinkage of relatively large voids experimentally observable in molybdenum at such temperatures may be easily explained in the framework of the present theory.

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Section: Introductionmentioning

confidence: 99%

Void nucleation at elevated temperatures under cascade-damage irradiation

Семенов

Woo

2002

Phys. Rev. B

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“…Molecular dynamics (MD) simulations studies using many-body potentials of the embedded atom method (EAM) type have proven to be very successful in the description of the first stage of damage production [2,3]. The modeling of the second stage has historically been undertaken by rate theory [4][5][6]. However, the application of kinetic Monte Carlo (kMC) simulations to diffusion processes [7,8] is starting to gain acceptance among the radiation damage community.…”

Section: Introductionmentioning

confidence: 99%

Simulation of damage evolution and accumulation in vanadium

Alonso¹,

Caturla²,

Rubia³

et al. 1999

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“…It took into account the vacancy loops produced by vacancy emission and biased interstitial absorptions. In this model, the dislocation bias (B d ) is still the dominant driving force for the irradiationinduced void swelling [4]. To model the effects of high energetic neutron irradiation, the more sophisticated production bias model [7e9] has been proposed.…”

Section: Introductionmentioning

confidence: 99%

Assessment of the dislocation bias in fcc metals and extrapolation to austenitic steels

Chang

Sandberg

Terentyev

et al. 2015

Journal of Nuclear Materials

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A systematic study of dislocation bias has been performed using a method that combines atomistic and elastic dislocation-point defect interaction models with a numerical solution of the diffusion equation with a drift term.Copper, nickel and aluminium model lattices are used in this study, covering a wide range of shear moduli and stacking fault energies. It is found that the dominant parameter for the dislocation bias in fcc metals is the width of the stacking fault ribbon. The variation in elastic constants does not strongly impact the dislocation bias value. As a result of this analysis and its extrapolation, the dislocation bias of the widely applied austenitic stainless steels of 316 type is predicted to be about 0.1 at temperature close to the swelling peak (815 K) and typical dislocation density of 10 14 m −2 . This is in line with the bias calculated using the elastic interaction model, whichEmail addresses: zhongwen@kth.se (Zhongwen Chang), polsson@kth.se (Pär Olsson)Preprint submitted to Journal of Nuclear Materials February 13, 2015 implies that the prediction method can be used readily in other fcc systems even without EAM potentials. By comparing the bias values obtained using atomistic-and elastic interaction energies, about 20% discrepancy is found, therefore a more realistic bias value for the 316 type alloy is 0.08 in these conditions.

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Recent advances in the understanding of damage production and its consequences on void swelling, irradiation creep and growth

Cited by 41 publications

References 72 publications

Void nucleation at elevated temperatures under cascade-damage irradiation

Void nucleation at elevated temperatures under cascade-damage irradiation

Simulation of damage evolution and accumulation in vanadium

Assessment of the dislocation bias in fcc metals and extrapolation to austenitic steels

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