1966
DOI: 10.1038/211291a0
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High-temperature Embrittlement of Stainless Steel irradiated in Fast Fluxes

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Cited by 17 publications
(3 citation statements)
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“…vacancies and interstitials56. These primary defects govern not only material microstructural changes, such as the formation of dislocation loops and voids789, but also material mechanical property changes10, for example embrittlement11, creep12 and hardening13. Although simulation studies have been performed for decades, reports of microstructural changes caused by the simultaneous presence of SVs and FPs are limited, except under ion-electron dual-beam irradiation14.…”
mentioning
confidence: 99%
“…vacancies and interstitials56. These primary defects govern not only material microstructural changes, such as the formation of dislocation loops and voids789, but also material mechanical property changes10, for example embrittlement11, creep12 and hardening13. Although simulation studies have been performed for decades, reports of microstructural changes caused by the simultaneous presence of SVs and FPs are limited, except under ion-electron dual-beam irradiation14.…”
mentioning
confidence: 99%
“…This phenomenon could also indicate an ability of the UFG steel to resist hightemperature radiation embrittlement typical to conventional CrNi steels. 67) Further investigations in the field are vitally needed to clarify uncovered gaps in exploring radiation tolerance issues concerning UFG and nanostructured materials, the effect of irradiation parameters (type, dose, temperature); the sink efficiency of different boundaries; the effect of defect distribution, precipitation and solute segregation in alloys with different chemical composition; different corrosion behaviour; and so on. On this basis, many additional ways to improve radiation tolerance of UFG materials could be found.…”
Section: Behaviour Of Ufg Materials Produced By Spd In the Conditions...mentioning
confidence: 99%
“…This top-down approach guarantees relatively good contact between the different crystallites and avoids electrical conductivity limitations (if required). Although the solubility of He in metals (including V) is extremely low, significant concentrations of implanted He can lead to dramatic changes in microstructure and mechanical properties [34,35]. Consequently, understanding the role of He in V systems is a critical issue in the development of structural materials for nuclear energy applications.…”
Section: Introductionmentioning
confidence: 99%