Void-swelling in cold-worked copper during HVEM irradiation

Leffers, T.; Singh, B.N.; Buckley, S.N.; Manthorpe, S. A.

doi:10.1016/0022-3115(83)90179-4

Cited by 12 publications

(7 citation statements)

References 1 publication

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Garner and his co-workers found that the cold working often accelerates the onset of void swelling in both bcc and fcc alloys [25][26][27], such as molybdenum and nickel. Leffers and his co-workers found a significant initial increase in void density and overall swelling value with the increased degree of cold work in pure copper [22]. At low cold work/strain levels, the introduced dislocations provide more nucleation sites for forming void embryos [22].…”

Section: Discussionmentioning

confidence: 96%

“…Similar results have been reported by Leffers. In his study, the copper was irradiated using a high-voltage electron microscope with a high dose rate of 0.006-0.010 dpa/s. The void density and total swelling value were significant initially increased with the increased degree of cold work in pure copper [22]. It is worth noting that, the dose rate of neutron irradiations in advanced fission reactors and fusion reactors is several orders of magnitude lower than that for ion irradiation, which can further move the system to the sink-dominated regime.…”

Section: Discussionmentioning

confidence: 98%

“…Leffers and his co-workers found a significant initial increase in void density and overall swelling value with the increased degree of cold work in pure copper [22]. At low cold work/strain levels, the introduced dislocations provide more nucleation sites for forming void embryos [22]. Void density and swelling value would level off, and eventually start decreasing with further cold work when vacancies can also reach the sinks easily.…”

Section: Discussionmentioning

confidence: 99%

See 2 more Smart Citations

Enhanced void swelling in NiCoFeCrPd high-entropy alloy by indentation-induced dislocations

Yang

Jin

et al. 2018

Materials Research Letters

View full text Add to dashboard Cite

The role of dislocations on ion irradiation-induced void formation is studied in a high-entropy alloy (HEA) NiCoFeCrPd. Despite previous observations that show high-entropy alloys are swelling resistant due to a high defect recombination rate, the swelling is enhanced with increasing density of pre-existing dislocations at low strain levels that shortened transient duration before the onset of void swelling. Under certain irradiation conditions, a high density of dislocations may carry the material closer to the sink-dominated regime. Compared to another HEA NiCoFeCrMn, NiCoFeCrPd has a smaller loop size and higher loop density due to the stronger lattice distortion. IMPACT STATEMENTSwelling behavior in a newly designed high-entropy alloy NiCoFeCrPd has been studied for the first time. Void swelling is enhanced with increasing density of pre-existing dislocations in NiCoFeCrPd.

show abstract

Section: Discussionmentioning

confidence: 96%

Section: Discussionmentioning

confidence: 98%

Section: Discussionmentioning

confidence: 99%

See 1 more Smart Citation

Enhanced void swelling in NiCoFeCrPd high-entropy alloy by indentation-induced dislocations

Yang

Jin

et al. 2018

Materials Research Letters

View full text Add to dashboard Cite

show abstract

“…2 The link between the number of displaced atoms (DPA) and the resultant, long-term accumulation and evolution of radiation damage in the form of multiscale material defects has been the subject of a great number of studies, recently summarized in a comprehensive tome on nuclear materials. 3 Variations in the dose-property response of the same materials exposed to identical DPA have been observed as functions of temperature, 4 dose rate, 5 type of radiation, 6 duty cycle (beam rastering) of charged particle beams, [7][8][9] imposed stresses, 10 processing and resultant microstructure, 11 secondary precipitates or impurities, 12 and coinjection or cogeneration of gases such as helium during irradiation. 13,14 These variations demonstrate a clear difference between applied dose and accumulated damage for differing material and irradiation conditions.…”

Section: Introductionmentioning

confidence: 98%

Applications of Transient Grating Spectroscopy to Radiation Materials Science

Short

Dennett

Ferry

et al. 2015

JOM

View full text Add to dashboard Cite

The ability to study radiation damage in situ will directly enable the rapid innovation and qualification of materials for nuclear applications by allowing direct observation of the effects of radiation damage accumulation. This is a challenging task, as the measurement technique must be noncontact, nondestructive, rapid, and still allow for online irradiation without interference. Applicable methods of mechanical spectroscopy are surveyed, noting their potential usefulness for characterizing radiation-induced microstructural changes in situ. The transient grating (TG) spectroscopy technique appears most suited for these studies, due to its noncontact, nondestructive nature, its ability to rapidly probe materials to the depth of ion irradiation, and the large number of deconvolvable components extractable from its signal. Work is proposed to separate the individual mechanisms of irradiation damage using in situ and ex situ TG spectroscopy, through a suite of single-effect and integrated experiments.

show abstract

“…For example, interstitials, being more mobile than the vacancies, are quickly absorbed by nearby dislocations, inducing creep by dislocation climb and dislocation multiplication that result in work hardening and embrittlement. Likewise, a small excess of remnant vacancies can agglomerate, leading to the formation of voids that cause swelling [1][2][3][4][5][6], an increase in residual stresses, microcrack formation, and the eventual failure of the material. The long-term stability of a microstructure under irradiation depends on its neutrality toward defect absorption.…”

Section: Introductionmentioning

confidence: 98%

Preferential void formation at crystallographically ordered grain boundaries in nanotwinned copper thin films

et al. 2015

View full text Add to dashboard Cite

a b s t r a c tNanocrystalline materials are expected to have improved radiation resistance as the high density of grain boundary area is thought to act as an effective sink for radiation-induced defects. However, continued absorption of defects can alter the structure of grain boundaries and/or enhance their mobility, eventually leading to microstructural degradation in the form of grain coarsening, thus negating their initial radiation tolerance. Hence, an ideal microstructure might be one with a mix of boundaries that are effective sinks and limit grain coarsening. We show through in situ electron irradiation experiments, however, that this is an insufficient condition. Our observations indicate that even a high density of low energy coherent twin boundaries, supposedly stabilizing the microstructure against grain coarsening, can be a detriment in that it biases the mobility of vacancies accumulating during irradiation thereby resulting in preferential void nucleation near twin boundaries. These observations highlight the fact that radiation induced grain boundary migration depends greatly on the topology of the grain boundary network and that the migration of high-angle grain boundaries can be hindered when coordinated at triple junctions composed of at least two low-energy boundaries, e.g., coincidence site lattice boundaries.

show abstract

Void-swelling in cold-worked copper during HVEM irradiation

Cited by 12 publications

References 1 publication

Enhanced void swelling in NiCoFeCrPd high-entropy alloy by indentation-induced dislocations

Enhanced void swelling in NiCoFeCrPd high-entropy alloy by indentation-induced dislocations

Applications of Transient Grating Spectroscopy to Radiation Materials Science

Preferential void formation at crystallographically ordered grain boundaries in nanotwinned copper thin films

Contact Info

Product

Resources

About