The microstructure and associated tensile properties of irradiated fcc and bcc metals

Victoria, M.; Baluc, N.; Bailat, Claude; Dai, Yong; Luppo, M.I.; Schäublin, R.; Singh, B.N.

doi:10.1016/s0022-3115(99)00203-2

Cited by 316 publications

(174 citation statements)

References 19 publications

Supporting

Mentioning

160

Contrasting

Unclassified

Order By: Relevance

“…In the more extreme cases of localized plastic deformation, the plastic strain is confined almost entirely to these narrow channels. The post-deformation microstructure of irradiated materials exhibiting a prominent yield drop clearly demonstrates that the plastic deformation is initiated in a very localized fashion and confined almost exclusively to the "cleared" channels (see Luft 1991 andVictoria et al 2000 for a review). The observation of these channels was first reported by Greenfield and Wilsdorf (1961).…”

Section: Introductionmentioning

confidence: 99%

Initiation and propagation of cleared channels in neutron-irradiated pure copper and a precipitation hardened CuCrZr alloy

Edwards

Singh

Bilde-Sørensen

2005

Journal of Nuclear Materials

View full text Add to dashboard Cite

(max. 2000 char.):The phenomenon of plastic flow localization in the form of "cleared" channels has been frequently observed in neutron irradiated metals and alloys for more than 40 years. So far, however, no experimental evidence as to how and where these channels are initiated during postirradiation deformation has emerged. Recently we have studied the problem of initiation and propagation of cleared channels during post-irradiation tensile tests of pure copper and a copper alloy irradiated with fission neutrons. Tensile specimens of pure copper and a precipitation hardened copper alloy (CuCrZr) were neutron irradiated at 323 and 373K to displacement doses in the range of 0.01 to 0.3 dpa (displacement per atom) and tensile tested at the irradiation temperature. The stress-strain curves clearly indicated the occurrence of a yield drop. The post-deformation microstructural examinations revealed that the channels are formed already in the elastic regime and their density increases with increasing plastic strain. The channels appear to have been initiated at grain boundaries, twin boundaries, at relatively large inclusions and even at the previously formed cleared channels. Even though the channels are produced throughout the whole tensile test, no clear evidence has been found for the operation of Frank-Read sources in the volume between the channels. Channels have been observed to penetrate through annealing twins, in some cases stopping at the opposite twin boundary and in other cases penetrating even through the opposite twin boundary and continuing further into the grain. In some cases channels have been found to penetrate through grain boundaries too. It is suggested that the high stress levels reached during deformation of the irradiated specimens activate dislocation sources at the sites of stress concentration at the boundaries and inclusions. The propagation of these newly generated dislocations in the matrix causes the formation of cleared channels. Implications of these results are discussed with specific reference to the origin and consequences of plastic flow localization.

show abstract

Section: Introductionmentioning

confidence: 99%

Initiation and propagation of cleared channels in neutron-irradiated pure copper and a precipitation hardened CuCrZr alloy

Edwards

Singh

Bilde-Sørensen

2005

Journal of Nuclear Materials

View full text Add to dashboard Cite

show abstract

“…Especially significant differences in the radiation sensitivity of the fcc and bcc crystal have been observed by computer simulation or experimental studies under irradiation conditions. [2][3][4][5][6] In this sense, the integrity of the weld is very important to the nuclear components made of stainless steel, and it is necessary to characterize the radiation sensitivity of the delta(δ)-ferrite compared with the fcc austenite matrix in the stainless steel welds under irradiation conditions as an input for the safety and lifetime evaluation of the welded stainless steel reactor component.…”

Section: Introductionmentioning

confidence: 99%

Influence of Ion-Irradiation on Hardness Change in Type 304 Stainless Steel Weldment Containing Delta(δ) Ferrite

Chi

Shin²,

Kim

et al. 2002

Mater. Trans.

View full text Add to dashboard Cite

Differences of high energy-ion induced microstructure of bcc δ-ferrite and fcc austenite matrix, and the effects of δ-ferrite on the Vickers micro-hardness (Hv) after irradiation were investigated for Type 304 stainless steel weldments containing two different δ-ferrite contents: ferrite number (FN) 5.5 and 8.5, respectively. Specimens were irradiated to 1.5 dpa with 8 MeV Fe +4 ions using a Tandem Vande-Graff accelerator (flux: 4.3×10 10 ion/cm 2 ·s, fluence: 0.83×10 15 ion/cm 2 ) at below 60 • C. Calculations TRIM 95 showed that a peak damage appeared at 1.5 µm in depth with 0.7 µm full width at half maximum (FWHM). These results on irradiation-induced defects (IIDs) distribution were confirmed by TEM. Clear differences for the size and number density of IIDs as black dots (size: 5-10 nm) and loops were observed in both the austenitic matrix and δ-ferrite, where the size of IIDs was far larger in the fcc matrix than the bcc δ-ferrite. Hv test results showed that the irradiation hardening of δ-ferrite was about 1.5 times larger than the austenitic matrix. From microstructural observation the increase of the higher Vickers micro-hardness was explained.

show abstract

“…Irradiation hardening is due to the production of crystalline defects, that can be of vacancy-type (e.g. Stacking Fault Tetrahedra (SFT) in copper [2,3]) or of interstitial-type (e.g. Frank loops in stainless steels (SS) [4]).…”

mentioning

confidence: 99%

Atomic-scale plasticity in the presence of Frank loops

Nogaret

Robertson

Rodney

2007

Philosophical Magazine

View full text Add to dashboard Cite

The microstructure and associated tensile properties of irradiated fcc and bcc metals

Cited by 316 publications

References 19 publications

Initiation and propagation of cleared channels in neutron-irradiated pure copper and a precipitation hardened CuCrZr alloy

Initiation and propagation of cleared channels in neutron-irradiated pure copper and a precipitation hardened CuCrZr alloy

Influence of Ion-Irradiation on Hardness Change in Type 304 Stainless Steel Weldment Containing Delta(δ) Ferrite

Atomic-scale plasticity in the presence of Frank loops

Contact Info

Product

Resources

About

The microstructure and associated tensile properties of irradiated fcc and bcc metals

Cited by 316 publications

References 19 publications

Initiation and propagation of cleared channels in neutron-irradiated pure copper and a precipitation hardened CuCrZr alloy

Initiation and propagation of cleared channels in neutron-irradiated pure copper and a precipitation hardened CuCrZr alloy

Influence of Ion-Irradiation on Hardness Change in Type 304 Stainless Steel Weldment Containing Delta(&delta;) Ferrite

Atomic-scale plasticity in the presence of Frank loops

Contact Info

Product

Resources

About

Influence of Ion-Irradiation on Hardness Change in Type 304 Stainless Steel Weldment Containing Delta(δ) Ferrite