2004
DOI: 10.1016/j.jnucmat.2004.04.298
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Observation and analysis of defect cluster production and interactions with dislocations

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Cited by 225 publications
(123 citation statements)
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“…bridge the DD and continuum crystal plasticity to predict the mechanical behavior in irradiated structural materials [8][9][10][11]. The scale-dependent effects of grain size on dislocation movement and yield stress have been predicted and agree with the experimental observation.…”
Section: Hierarchical Upscaling Methods For Irradiation Strengthening supporting
confidence: 57%
See 1 more Smart Citation
“…bridge the DD and continuum crystal plasticity to predict the mechanical behavior in irradiated structural materials [8][9][10][11]. The scale-dependent effects of grain size on dislocation movement and yield stress have been predicted and agree with the experimental observation.…”
Section: Hierarchical Upscaling Methods For Irradiation Strengthening supporting
confidence: 57%
“…This relationship is slightly different from the dispersed barrier model's theoretical prediction [8][9][10], which is based on geometrical considerations for strong obstacles intersecting the dislocation glide planes, where the yield strength increase,   , is proportional to the square root of defect cluster density, d:…”
Section: Hierarchical Upscaling Methods For Irradiation Strengthening mentioning
confidence: 58%
“…96 Radiation hardening in copper can be adequately described by Seeger's dispersed barrier model, and the yield strength increase is due to the formation of defect clusters. 98 Singh and Zinkle 96 summarized the dose dependence of the TEM-visible defect cluster density in copper irradiated near room temperature with fission neutrons, 14 MeV neutrons, spallation neutrons, and 800 MeV protons ( Figure 15) 96 TEMvisible defect clusters were observed at a very low dose (10 -5 dpa). The defect cluster density showed a linear dependence on irradiation dose at low doses.…”
Section: Effect Of Irradiation Onmentioning
confidence: 99%
“…Radiation hardening and embrittlement that occurs in metals irradiated at low temperatures (below ~0.3 T m , where T m is the melting temperature) is a an important technical challenge for advanced nuclear energy systems (Zinkle and Matsukawa 2004). In this example, the Visco Plastic Self Consistent (VPSC) polycrystalline code (Lebensohn and Tome 1993) is employed in order to model the yield stress dependence in ferritic steels on the irradiation dose.…”
Section: Microstructural Mechanics Of Irradiation Hardeningmentioning
confidence: 99%
“…Two approximate dislocation barrier models have historically been used to describe radiation hardening in metals (Zinkle and Matsukawa 2004) and are reviewed in (Koppenaal and Arsenault 1971;Kocks 1977). The dispersed barrier model (Seeger, Diehl et al 1957) is based on straightforward geometrical considerations for obstacles intersecting the dislocation glide plane and it is most appropriate for strong obstacles.…”
Section: Microstructural Mechanics Of Irradiation Hardeningmentioning
confidence: 99%