The inhomogeneous deformation behaviour of neutron irradiated Zircaloy-2

Onchi, Takeo; Kayano, Hideo; Higashiguchi, Yasuhiro

doi:10.1016/0022-3115(80)90278-0

Cited by 61 publications

(40 citation statements)

References 4 publications

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“…The Stage V temperature is higher than T da because the vacancy binding energy varies with cluster size and the damage structures in PIA studies are usually more mature than the more embryonic clusters involved in dynamic annealing. Literature data indicate that the effective Stage V temperature for bcc ferritic steels is 300-400 o C [72], and is 350-400 o C for Zircaloy [73,74]. For austenitic stainless steels the picture is not so clear.…”

Section: Discussion Of Phase 3 Findingsmentioning

confidence: 99%

MAPPING FLOW LOCALIZATION PROCESSES IN DEFORMATION OF IRRADIATED REACTOR STRUCTURAL ALLOYS - FINAL REPORT. Nuclear Energy Research Initiative Program No. MSF99-0072. Period: August 1999 through September 2002. (ORNL/TM-2003/63)

Farrell¹

2003

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Section: Discussion Of Phase 3 Findingsmentioning

confidence: 99%

MAPPING FLOW LOCALIZATION PROCESSES IN DEFORMATION OF IRRADIATED REACTOR STRUCTURAL ALLOYS - FINAL REPORT. Nuclear Energy Research Initiative Program No. MSF99-0072. Period: August 1999 through September 2002. (ORNL/TM-2003/63)

Farrell¹

2003

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“…The inhomogeneous plastic deformation due to dislocation channels is strongly related to the significant irradiation hardening. 21,22) One of the reasons why deformation in irradiated material is inhomogeneous is the local slip deformation due to dislocation channeling formation in which dislocation movement sweep out the defect clusters produced by neutron irradiation. 23,24) The ductility loss in neutron-irradiated metals strongly concerned with the non-uniform deformation mode induced by radiation damage.…”

Section: °°C 300°c 400°cmentioning

confidence: 99%

Effects of Impurities on Microstructural Evolution and Deformation Process of Ion-Irradiated V–Cr–Ti Alloys

et al. 2005

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Microstructural examination and microhardness test were carried out for unalloyed vanadium, V-5Ti, V-4Cr-4Ti alloys irradiated with 4 MeV Cu ions at temperatures from 200 to 600 C. In order to investigate the impurity effect, high purification technique was used. Impurity effects can be seen in the nucleation and growth processes of voids in unalloyed vanadium and those of Ti(OCN) precipitates in V-5Ti. The changes in microstructure due to interstitial impurity could not be seen in V-4Cr-4Ti after the irrodiations below 300 C. The effect of impurity for irradiation hardening in ion-irradiated V-4Cr-4Ti alloys could be seen at 400 C, but it could not be seen at 200 and 300 C. On the other hand, dislocation channels were observed at 200 and 300 C, and the total length of dislocation channels became larger as the impurity level increased. It can be considered that there was practically no correlation between irradiation hardening and total length of dislocation channels due to impurity effects.

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“…In tensile experiments on steels, the dominant deformation mechanism is found to change from twinning to dislocation channeling with increasing temperature (21,22). In tensile experiments on Zircaloy-2, the width of the dislocation channels is observed to be larger at high temperature than at low temperature (26). These various deformation mechanisms shown in Fig.…”

Section: Discussionmentioning

confidence: 87%

“…An issue currently exists in reconciling the results of atomistic MD simulations with experiments because of the time-scale gap between them, whereas it is known that both strain rate and temperature affect the interaction mechanism and critical stresses (1,4,8,12,(20)(21)(22)(23)(24)(25)(26)(27). Methods alternative to MD exist, some based on surveying the potential energy surface coupled with variants of kinetic Monte Carlo (28,29) and some based on escaping from the deep energy minima in dynamics simulations (30)(31)(32).…”

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confidence: 99%

Mapping strain rate dependence of dislocation-defect interactions by atomistic simulations

Fan¹,

Osetsky

Yip

et al. 2013

Proc. Natl. Acad. Sci. U.S.A.

102

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Probing the mechanisms of defect-defect interactions at strain rates lower than 10 6 s −1 is an unresolved challenge to date to molecular dynamics (MD) techniques. Here we propose an original atomistic approach based on transition state theory and the concept of a strain-dependent effective activation barrier that is capable of simulating the kinetics of dislocation-defect interactions at virtually any strain rate, exemplified within 10 −7 to 10 7 s −1 . We apply this approach to the problem of an edge dislocation colliding with a cluster of self-interstitial atoms (SIAs) under shear deformation. Using an activation-relaxation algorithm [Kushima A, et al. (2009) J Chem Phys 130:224504], we uncover a unique strain-ratedependent trigger mechanism that allows the SIA cluster to be absorbed during the process, leading to dislocation climb. Guided by this finding, we determine the activation barrier of the trigger mechanism as a function of shear strain, and use that in a coarsegraining rate equation formulation for constructing a mechanism map in the phase space of strain rate and temperature. Our predictions of a crossover from a defect recovery at the low strainrate regime to defect absorption behavior in the high strain-rate regime are validated against our own independent, direct MD simulations at 10 5 to 10 7 s −1 . Implications of the present approach for probing molecular-level mechanisms in strain-rate regimes previously considered inaccessible to atomistic simulations are discussed.structural materials | mechanical properties | low strain rate atomistic simulation

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The inhomogeneous deformation behaviour of neutron irradiated Zircaloy-2

Cited by 61 publications

References 4 publications

MAPPING FLOW LOCALIZATION PROCESSES IN DEFORMATION OF IRRADIATED REACTOR STRUCTURAL ALLOYS - FINAL REPORT. Nuclear Energy Research Initiative Program No. MSF99-0072. Period: August 1999 through September 2002. (ORNL/TM-2003/63)

MAPPING FLOW LOCALIZATION PROCESSES IN DEFORMATION OF IRRADIATED REACTOR STRUCTURAL ALLOYS - FINAL REPORT. Nuclear Energy Research Initiative Program No. MSF99-0072. Period: August 1999 through September 2002. (ORNL/TM-2003/63)

Effects of Impurities on Microstructural Evolution and Deformation Process of Ion-Irradiated V–Cr–Ti Alloys

Mapping strain rate dependence of dislocation-defect interactions by atomistic simulations

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The inhomogeneous deformation behaviour of neutron irradiated Zircaloy-2

Cited by 61 publications

References 4 publications

MAPPING FLOW LOCALIZATION PROCESSES IN DEFORMATION OF IRRADIATED REACTOR STRUCTURAL ALLOYS - FINAL REPORT. Nuclear Energy Research Initiative Program No. MSF99-0072. Period: August 1999 through September 2002. (ORNL/TM-2003/63)

MAPPING FLOW LOCALIZATION PROCESSES IN DEFORMATION OF IRRADIATED REACTOR STRUCTURAL ALLOYS - FINAL REPORT. Nuclear Energy Research Initiative Program No. MSF99-0072. Period: August 1999 through September 2002. (ORNL/TM-2003/63)

Effects of Impurities on Microstructural Evolution and Deformation Process of Ion-Irradiated V&ndash;Cr&ndash;Ti Alloys

Mapping strain rate dependence of dislocation-defect interactions by atomistic simulations

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Effects of Impurities on Microstructural Evolution and Deformation Process of Ion-Irradiated V–Cr–Ti Alloys