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Characterization of ODS Steels after Gamma Irradiation for Application in ALLEGRO Reactor

100%
Slugeň V., Bartošová I., Dekan J.
Acta Physica Polonica A
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2017
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vol. 131
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issue 4
1090-1092
EN
Oxide-dispersion strengthened steels characterization using various spectroscopic techniques is presented. Microstructure of 15% chromium oxide-dispersion strengthened steels was studied in term of vacancy defects presence and their accumulation after defined irradiation treatment, respectively. Studied materials originated from Kyoto University and studied via IAEA collaborative project focused on generation IV reactors (ALLEGRO). Samples were characterized "as received" by positron annihilation lifetime spectroscopy, the Mössbauer spectroscopy and their microstructure was examined by transmission electron microscopy as well. Samples were afterwards irradiated in Washington State University Nuclear Radiation Center via a strong gamma source (6 TBq). Damage induced by gamma irradiation was evaluated by positron lifetime measurements in emphasis on defect accumulation in the materials. We have demonstrated strong defect production induced by gamma irradiation which results from positron measurement data.
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Vickers Hardness and Positron Annihilation Study of Eurofer97 and ODS Eurofer

100%
Bartošová I., Čížek J., Lukáč F., Slugeň V.
Acta Physica Polonica A
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2014
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vol. 125
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issue 3
702-705
EN
This paper describes investigations of Eurofer97 and oxide dispersion strengthened version of this steel, in as received state and after annealing. Vickers hardness test was performed on the as received specimens and after annealing at various temperatures to obtain information about development of the strength of studied materials. After identifying the temperature region where significant changes of the strength take place we applied positron annihilation spectroscopy to probe the microstructural changes in ferritic/martensitic steels. An observation of phase transformation was observed in both steels at various temperatures indicating different behaviour of the base material and its strengthened version. All applied methods proved the importance of strengthening by oxides to improve properties of steels.
3
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German and Russian Irradiated Reactor Pressure Vessel Steels from PAS Point of View

64%
Slugeň V., Hein H., Sojak S., Pecko S., Šimeg Veterníková J., Petriska M., Sabelová V., Bartošová I., Stacho M.
Acta Physica Polonica A
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2014
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vol. 125
|
issue 3
726-728
EN
This paper presents a comparison of commercially used German and Russian reactor pressure vessel steels from the positron annihilation spectroscopy point of view, having in mind knowledge obtained also from other techniques from the last decades. The second generation of Russian reactor pressure vessel steels seems to be fully comparable with German steels and their quality allows prolongation of NPP operating lifetime over projected 40 years. The embrittlement of CrMoV steels is very low due to the dynamic recovery of radiation-induced defects at reactor operating temperatures. Positron annihilation spectroscopy techniques can be effectively applied for evaluation of microstructural changes caused by extreme external loads by proton implantation, with aim to simulate irradiation and for the evaluation of the effectiveness of post-irradiation thermal treatments. We used our actual and previous results, collected during last 20 years from measurements of different reactor pressure vessel steels in "as received", irradiated and post-irradiation annealed state and compare them with the aim to contribute to general knowledge based on experimental positron annihilation spectroscopy data.
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