18-22 July 2016
Hotel Wyndham Grand Axelmannstein, Bad Reichenhall, Germany
Europe/Berlin timezone

PAS studies of neutron and hydrogen treated reactor steels

21 Jul 2016, 11:50
Contributed Engineering & Industrial applications Session X: Engineering (Chair: Ralph Gilles)


Prof. Vladimir Slugen (FEI STU Bratislava)


Nuclear materials degradation caused by radiation exposure can be experimentally simulated via ion implantation. In our case, German reactor pressure vessel (RPV) steels were studied by positron annihilation lifetime spectroscopy (PALS). This unique non-destructive method can be effectively applied for the evaluation of microstructural changes and for the analysis of degradation of reactor steels due to neutron irradiation and proton implantation. Studied specimens of German reactor pressure vessel steels are originally from CARINA/CARISMA program. Eight specimens were measured in as-received state and two specimens were irradiated by neutrons in German experimental reactor VAK (Versuchsatomkraftwerk Kahl) in the 1980s. One of the specimens which was in as-received and neutron irradiated condition was also used for simulation of neutron damage by hydrogen nuclei implantation. Defects with the size of about 1-2 vacancies with relatively small contribution (with intensity on the level of 20-40 %) were observed in “as-received” steels. A significant increase in the size of the induced defects due to neutron damage was observed in the irradiated specimens resulting in 2-3 vacancies. The size and intensity of defects reached a similar level as in the specimens irradiated in the nuclear reactor due to the implantation of hydrogen ions with energies of 100 keV (up to the depth <500 nm). Actual results from German reactor steels were compared to previous experiences with Russian and Japan reactor steels studied after different loads. Acknowledgment This article was created with the support of the Ministry of Education, Science, Research and Sport of the Slovak Republic within the Research and Development Operational Programme for the project "University Science Park of STU Bratislava", ITMS 26240220084, co-funded by the European Regional Development Fund. This article was also granted by VEGA 1/0204/13. References [1] H. Hein, E. Keim, H. Schnabel. T. Seibert, A. Gundermann, J. ASTM Int. 6 (2009) Paper ID JAI101962 [2] V. Slugeň, Safety of VVER-440 Reactors – Barriers Against Fission Products Release, Springer, 2011, ISBN 978-1-84996-419-7 [3] V. Slugen, V. Krsjak, W. Egger, M.Petriska, S.Sojak and J. Vetrenikova, J. Nucl. Mater. 409 (2011) 163

Primary author

Prof. Vladimir Slugen (FEI STU Bratislava)


Dr Martin Petriska (FEI STU) Mr Stanislav Pecko (FEI STU Bratislava) Dr Stanislav Sojak (FEI STU)

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