Swelling and microstructure of pure Fe and Fe–Cr alloys after neutron irradiation to ∼26dpa at 400°C

Konobeev, Yu. V.; Dvoriashin, A. M.; Porollo, S. I.; Garner, F.А.

doi:10.1016/j.jnucmat.2006.04.011

Cited by 81 publications

(36 citation statements)

References 7 publications

(13 reference statements)

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“…Effects of SRO on the electrical resistivity of alloys have been studied theoretically and experimentally before [24,26,39]. For example, resistivity increases by 20-30% with the formation of SRO in NiCu alloys [42], which is not as markedly in NiCoCr compared with binary NiCo.…”

mentioning

confidence: 99%

Local Structure and Short-Range Order in a NiCoCr Solid Solution Alloy

et al. 2017

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mentioning

confidence: 99%

Local Structure and Short-Range Order in a NiCoCr Solid Solution Alloy

et al. 2017

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“…However, in the case of concentrated alloys, the presence of migrating defects allows solute rearrangements and changes in the SRO, which in turn affect the residual resistivity of the alloy. This effect might thus significantly alter the RR results and their interpretation, as it has been discussed in the case of Fe-Cr [18,19].In the field of energy advanced materials development there is specific interest in the study of Cr effects on nuclear alloys [20,21], given that Cr concentrations (C Cr ) close to 9% reduce swelling [22,23], reduce the radiation-induced ductile-brittle transition temperature (DBTT) [24], and increase protection against corrosion [25]. The physics of these effects is not yet well understood though it is believed that the minimum of the SRO parameters might play a role in affecting the kinetics of radiation defects in a concentrated Fe-Cr system.…”

mentioning

confidence: 99%

“…In the field of energy advanced materials development there is specific interest in the study of Cr effects on nuclear alloys [20,21], given that Cr concentrations (C Cr ) close to 9% reduce swelling [22,23], reduce the radiation-induced ductile-brittle transition temperature (DBTT) [24], and increase protection against corrosion [25]. The physics of these effects is not yet well understood though it is believed that the minimum of the SRO parameters might play a role in affecting the kinetics of radiation defects in a concentrated Fe-Cr system.…”

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confidence: 99%

Decoupling of defect and short-range order contributions to resistivity recovery measurements in binary alloys

et al. 2014

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We report a new and improved approach that uses low-temperature resistivity recovery measurements to study the defect kinetics in metallic binary alloys. This method is able to decouple the effect related to the irradiation defect contribution to the resistivity from that of the short-range order, which is enhanced by the free migration of defects. This approach can provide reliable experimental data which are more suitable for comparisons with current computational models. Furthermore, the difference in this method with respect to the classical one is that our method gives information concerning the role of vacancies and interstitials on short-range order. The method is applied to a model alloy Fe-5%Cr, of interest for fusion applications, where short-range order effects have been previously found to play a role. In general, concentrated alloys have enough solute concentration to perturb the electronic structure and the phonon spectrum. Typically this composition range starts at 1%-2% of the solute concentration. These perturbations lead to an atomic configuration which is never fully random; there are certain atomic correlations that can be described as short-range order (SRO). The SRO parameters (α i ) are defined as the correlation between first-and next-nearest neighbors (NN) of an atom [1]. Every alloy has different SRO equilibrium configurations for every solute concentration and temperature [2], which also depend on the thermomechanical process experienced [3,4]. Quenching experiments have been widely used to study the kinetics of ordering [2][3][4][5][6][7][8] given the linear relation of the resistivity (ρ) with α i (cf. Refs. [1,8]). Concurrently, resistivity recovery (RR) experiments have been commonly used to investigate radiation effects in pure metals, based on the recovery of the residual resistivity up to its original value after low-temperature irradiation and subsequent isochronal annealing [9][10][11][12][13][14][15][16][17]. However, in the case of concentrated alloys, the presence of migrating defects allows solute rearrangements and changes in the SRO, which in turn affect the residual resistivity of the alloy. This effect might thus significantly alter the RR results and their interpretation, as it has been discussed in the case of Fe-Cr [18,19].In the field of energy advanced materials development there is specific interest in the study of Cr effects on nuclear alloys [20,21], given that Cr concentrations (C Cr ) close to 9% reduce swelling [22,23], reduce the radiation-induced ductile-brittle transition temperature (DBTT) [24], and increase protection against corrosion [25]. The physics of these effects is not yet well understood though it is believed that the minimum of the SRO parameters might play a role in affecting the kinetics of radiation defects in a concentrated Fe-Cr system. Indeed, it has been proven that α i change their sign at C Cr close to 10% [26][27][28]. At C Cr < 11% the SRO becomes negative, i.e., Cr tends to distribute as far * begona.gomez-ferrer@externos.ciemat.es...

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“…The Fe-18wt.%Cr alloy is reported to be a pure ferrite phase without carbides (i.e. M 23 C 6 or MX) [25]. Figure 3(a) shows internal friction spectra of the asreceived, 1, 2, and 4 passes Fe-18wt.%Cr specimens.…”

Section: Fe-18wt%cr Steelmentioning

confidence: 99%

Mechanical Spectroscopy Of Equal-Channel Angular Pressed Fe-Cr Alloys And Tungsten

Hao¹,

Tang²,

Jiang³

et al. 2015

Archives of Metallurgy and Materials

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Internal friction technique was used to investigate the microstructural stability of equal-channel angular pressed (ECAP) 9Cr1Mo steel (T91), Fe-18wt.%Cr alloy, and pure W. Several non-relaxation internal friction peaks are observed in three ECAP-strained specimens, which are related to the microstructural transition from a severely deformed state to a static recovery state of dislocations, and to recrystallized state. Along with the disappearance of the P1 peak, another relaxation internal friction peak P2 is observed during the second heating run only in Fe-18wt.%Cr alloy, and it does not disappear even during subsequent third heating run. This peak is not observed in T91 steel and W. The P2 peak is likely associated with a process of grain boundary (GB) sliding. Unlike T91, no abundant carbide precipitates distribute on GBs to pin GB and repulse GB sliding, thus, the P2 peak only occurs in Fe-18wt.%Cr alloy. It is concluded that high-temperature internal friction measurements are required to detect the grain boundary peak in pure W.

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Swelling and microstructure of pure Fe and Fe–Cr alloys after neutron irradiation to ∼26dpa at 400°C

Cited by 81 publications

References 7 publications

Local Structure and Short-Range Order in a NiCoCr Solid Solution Alloy

Local Structure and Short-Range Order in a NiCoCr Solid Solution Alloy

Decoupling of defect and short-range order contributions to resistivity recovery measurements in binary alloys

Mechanical Spectroscopy Of Equal-Channel Angular Pressed Fe-Cr Alloys And Tungsten

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