Kinetics of low-temperature radiation hardening of metallic materials under irradiation

Platov, Yu. V.; Lazorenko, V.M.; Tovtin, V. I.; Khasanov, F. A.

doi:10.1134/s2075113311020171

Cited by 4 publications

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“…6. For values of M=2.75 (for bcc crystals) [27], and α=0.25∼0.50 we obtain increases in yield stress that range between 137 MPa at 600 • C and 8 MPa at 550 • C. The actual range of ∆σ values for each temperature is given in Table 1. It is worth mentioning that voids and He bubbles are likely to have their own non-negligible contribution to hardening.…”

Section: Sia Loop Hardeningmentioning

confidence: 82%

Modeling fast neutron irradiation damage accumulation in tungsten

Marian

Hoang

2012

Journal of Nuclear Materials

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Due to its advantageous physical properties, tungsten (W) is being considered as a candidate structural material in fusion applications. In this paper, we perform stochastic cluster dynamics calculations of irradiation damage accumulation in pure W under fast neutron spectra in up to doses of 1.5 dpa in the 400∼600 • C interval. Our calculations suggest that He bubbles and dislocation loops accumulate under fusion conditions, but not under fast fission spectra. We study the temperature dependence of swelling and find that it is maximum in the 550∼590 • C temperature range, falling precipitously above 600 • C. Swelling levels are very low, never surpassing a fraction of a percentage point. We also provide hardening estimates based on the accumulation of sessile dislocation loops under fusion conditions and show that they are moderate, ranging between 70 and 137 MPa at 400 • C.

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Section: Sia Loop Hardeningmentioning

confidence: 82%

Modeling fast neutron irradiation damage accumulation in tungsten

Marian

Hoang

2012

Journal of Nuclear Materials

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“…The second term on the right hand side describes the growth process of dislocation loops. The validity of this mechanism and its parameters were repeatedly confirmed in analyzing the experiments on irradiation of V, Ti, Al, and its solid solutions Al-Zn, Al-Sc, and Al-Mg when irradiated with electrons with energies of 1 and 2.2 MeV at temperatures of 293-343 K [1][2][3][4][5][6][7][8][9]. At the same time, a correct mechanism of the dislocation loop formation which allows deter…”

Section: Introductionmentioning

confidence: 97%

“…The sat uration is reached at such irradiation doses where the fluxes of interstitial atoms and vacancies on the loops become equal to one another. According to (2) and (3), the input rate of freely migrating point defects is G = ab.…”

Section: Introductionmentioning

confidence: 99%

“…Within this model, the general formula describing growth and nucleation of loops has the form (1) where is the total concentration of interstitial atoms in loops in the irradiation interval t and C 0 is the total concentration of interstitial atoms in the dislocation loops created in their nucleation interval τ n . Parame ters a and b are given by (2) ( 3) where G is the input rate of freely migrating defects, inter stitials, and vacancies, and K v and K d are the constants of reactions of vacancy formation and dissociation.…”

Section: Introductionmentioning

confidence: 99%

“…These processes largely determine the kinetics of radiation hardening, embrittlement, and phase instability of irradiated metals and alloys [1][2][3].…”

Section: Introductionmentioning

confidence: 99%

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Nucleation of interstitial dislocation loops in metals under electron irradiation

Platov

2014

Inorg. Mater. Appl. Res.

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A hybrid model of the dislocation loop nucleation in metals during electron irradiation is pro posed. The model is based on the kinetic diffusion mechanism of formation and growth of three dimensional interstitial atomic clusters and the thermodynamic mechanism of intermittent transformation of these clus ters in dislocation loops. The existence of critical input rate G C of freely migrating point defects is established. When G < G C , loops of minimum size consisting of four atoms are formed at the stage of nucleation. With increasing G at G > G C , the number of interstitial atoms increases (n 0 ≥ 4). By analyzing experimental data for the electron irradiated aluminum, it is shown that, using the formulas of the proposed model, one can cal culate all parameters of nucleation of interstitial dislocation loops at a given magnitude of the input rate of freely migrating defects without performing experimental studies.

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Irradiation hardening behaviors of tungsten–potassium alloy studied by accelerated 3-MeVW²⁺ ions*

et al. 2020

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Tungsten–potassium (WK) alloy with ultrafine/fine grains and nano-K bubbles is fabricated through spark plasma sintering (SPS) and rolling process. In this study, 3-MeV W2+ ion irradiation with a tandem accelerator is adopted to simulate the displacement damage caused by neutrons. As the depth of irradiation damage layer is limited to only 500 nm, the hardening behaviors of WK alloy and ITER (International Thermonuclear Experimental Reactor)-W under several damage levels are investigated through Bercovich tip nanoindentation test and other morphological characterizations. The indenter size effect (ISE), soft substrate effect (SSE), and damage gradient effect (DGE) are found to influence the measurement of nano-hardness. Few or no pop-ins in irradiated samples are observed while visible pop-in events take place in unirradiated metals. Extensive pile-up with different morphology features around the indentation exists in both WK and ITER-W. The WK shows a smaller hardness increment than ITER-W under the same condition of displacement damage. This study provides beneficial information for WK alloy serving as a promising plasma facing materials (PFMs) candidate.

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Kinetics of low-temperature radiation hardening of metallic materials under irradiation

Cited by 4 publications

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Modeling fast neutron irradiation damage accumulation in tungsten

Modeling fast neutron irradiation damage accumulation in tungsten

Nucleation of interstitial dislocation loops in metals under electron irradiation

Irradiation hardening behaviors of tungsten–potassium alloy studied by accelerated 3-MeVW²⁺ ions*

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Kinetics of low-temperature radiation hardening of metallic materials under irradiation

Cited by 4 publications

References 0 publications

Modeling fast neutron irradiation damage accumulation in tungsten

Modeling fast neutron irradiation damage accumulation in tungsten

Nucleation of interstitial dislocation loops in metals under electron irradiation

Irradiation hardening behaviors of tungsten–potassium alloy studied by accelerated 3-MeVW2+ ions*

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Irradiation hardening behaviors of tungsten–potassium alloy studied by accelerated 3-MeVW²⁺ ions*