First simultaneous detection of helium and tritium inside bubbles in beryllium

Klimenkov, M.; Vladimirov, P.; Hoffmann, J.; Zimber, N.; Möslang, A.; Kuksenko, V.

doi:10.1016/j.micron.2019.102754

Cited by 15 publications

(5 citation statements)

References 39 publications

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“…(DF) image of a gas bubble (black) attached to an ODS-particle (grey) as well as a single lowloss EELS spectrum (upper right) from its interior after principle component analysis (PCA) [26]. The H-K edge is clearly visible at 12.9 eV which is in good accordance with other values reported in the literature [27][28][29]. The He-K edge, however, is only visible as a small shoulder near the plasmon peak of the metallic matrix around 23 eV.…”

Section: Analytical Transmission Electron Microscopysupporting

confidence: 86%

Microstructural evolution of three potential fusion candidate steels under ion-irradiation

Zimber

Vladimirov

Klimenkov

et al. 2020

Journal of Nuclear Materials

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Section: Analytical Transmission Electron Microscopysupporting

confidence: 86%

Microstructural evolution of three potential fusion candidate steels under ion-irradiation

Zimber

Vladimirov

Klimenkov

et al. 2020

Journal of Nuclear Materials

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“…www.nature.com/scientificreports/ It is known that besides Re and Os also H and He are generated in the low appm amounts by transmutation of impurities in W and its alloys 58,59 . From Be it is well-known that both elements are retained within the material in the form of gas-filled bubbles 60 . The same effect might be also valid for W, however, in an attenuated form.…”

Section: Discussionmentioning

confidence: 99%

New insights into microstructure of neutron-irradiated tungsten

Dürrschnabel

Klimenkov

Jäntsch

et al. 2021

Sci Rep

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The development of appropriate materials for fusion reactors that can sustain high neutron fluence at elevated temperatures remains a great challenge. Tungsten is one of the promising candidate materials for plasma-facing components of future fusion reactors, due to several favorable properties as for example a high melting point, a high sputtering resistivity, and a low coefficient of thermal expansion. The microstructural details of a tungsten sample with a 1.25 dpa (displacements per atom) damage dose after neutron irradiation at 800 °C were examined by transmission electron microscopy. Three types of radiation-induced defects were observed, analyzed and characterized: (1) voids with sizes ranging from 10 to 65 nm, (2) dislocation loops with a size of up to 10 nm and (3) W–Re–Os containing σ- and χ-type precipitates. The distribution of voids as well as the nature of the occurring dislocation loops were studied in detail. In addition, nano-chemical analyses revealed that the σ- and χ-type precipitates, which are sometimes attached to voids, are surrounded by a solid solution cloud enriched with Re. For the first time the crystallographic orientation relationship of the σ- and χ-phases to the W-matrix was specified. Furthermore, electron energy-loss spectroscopy could not unambiguously verify the presence of He within individual voids.

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“…It is known that besides Re and Os also H and He are generated in appm amounts by transmutation of impurities in W and its alloys 45,46 . From Be it is well-known that both elements are retained within the material in the form of gas-filled bubbles 47 . The same effect might be also valid for W, however, in an attenuated form.…”

Section: Discussionmentioning

confidence: 99%

New microstructural insights into neutron-irradiated tungsten

Dürrschnabel¹,

Klimenkov²,

Jäntsch³

et al. 2020

Preprint

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The development of appropriate materials for fusion reactors that can sustain high neutron fluencies at elevated temperatures remains a great challenge. Tungsten is one of the promising candidate materials for plasma-facing components of future fusion reactors, due to several favorable properties as for example a high melting point, a high sputtering resistivity, and a low coefficient of thermal expansion. The microstructural details of a tungsten sample with a 1.25 dpa (displacements per atom) damage dose after irradiation at 800°C were examined by transmission electron microscopy (TEM). Three types of radiation-induced defects were observed, analyzed and characterized: (i) voids with sizes ranging from 10 nm to 65 nm, (ii) dislocation loops with a size of up to 10 nm and (iii) W-Re-Os containing σ- and χ-type precipitates. The distribution of voids as well as the nature of the occurring dislocation loops were studied in detail. In addition, nano-chemical analyses revealed that the σ- and χ-type precipitates, which are sometimes attached to voids, are surrounded by a solid solution cloud enriched with Re. For the first time the crystallographic orientation relationship of the σ- and χ-phases to the W-matrix was specified. Furthermore, electron energy-loss spectroscopy could not unambiguously verify the presence of He within individual cavities.

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First simultaneous detection of helium and tritium inside bubbles in beryllium

Cited by 15 publications

References 39 publications

Microstructural evolution of three potential fusion candidate steels under ion-irradiation

Microstructural evolution of three potential fusion candidate steels under ion-irradiation

New insights into microstructure of neutron-irradiated tungsten

New microstructural insights into neutron-irradiated tungsten

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