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Mössbauer Spectroscopy Study of Laboratory Produced ODS Steels

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Degmová J., Dekan J., Šimeg Veterníková J., Slugeň V.
Acta Physica Polonica A
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2017
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vol. 131
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issue 4
1171-1173
EN
The investigated oxide dispersion strengthened steels were received from laboratories involved in the Coordinated Research Project F11014 "Benchmarking of Structural Materials Pre-selected for Advanced Nuclear Reactors", namely from India (IGCAR), Russia (Bochvar Institute), China (University of Beijing), and Japan (Kyoto University). The application of the Mössbauer spectroscopy on these materials is aimed to reveal the complex information about studied materials via unique characteristics as micromagnetic properties and homogeneity of admixtures distribution in steels. All studied steels mainly differ in content of elements as Cr or Al. Chosen fitting model consists of bcc Fe, bcc Fe with Cr substitution and paramagnetic bcc Cr rich components. These ODS steels are aimed in further study for He implantations.
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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
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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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