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Analysis of Mechanical Properties and Nanostructure Changes of VVER-440 Reactor Pressure Vessel Metal after Annealing

https://doi.org/10.56304/S2079562920060354

Abstract

Analysis of mechanical testing and microstructural investigations of the irradiated VVER-440 reactor pressure vessel (RPV) metal before and after annealing carried out in the frameworks of the international project “PRIMAVERA” is presented. The role of chemical elements (Cu and P) was studied in relation to irradiation embrittlement of the VVER-440 RPV weld metal in the initial state, after recovery annealing and after postannealing irradiation. It was shown that under primary irradiation, copper atoms formed small clusters (size ~1‒2 nm) which also include P, Si and Mn atoms. Phosphorus atoms also segregated on copper clusters, dislocations, grain boundaries, and additionally formed phosphorus clusters and atmospheres. Under thermal annealing at 475°C, the irradiation-induced copper-enriched and phosphorus clusters partially dissolved, increasing the copper concentration in the annealed metal, which was significantly lower compared to the unirradiated material. Since most copper atoms after annealing were not contained in the ferritic matrix but in precipitates, the contribution of copper atoms to an increase in the ductile-to-brittle transition temperature under re-irradiation was minimized and so hardening and embrittlement after subsequent post-annealing irradiation were lower than under primary irradiation.

About the Authors

А. М. Kryukov
Scientific and Engineering Centre for Nuclear and Radiation Safety
Russian Federation

Moscow, 107140



А. А. Chernobaeva
National Research Center “Kurchatov Institute”
Russian Federation

Moscow, 123182



D. Yu. Erak
National Research Center “Kurchatov Institute”
Russian Federation

Moscow, 123182 



S. V. Rogozhkin
Kurchatov Complex for Theoretical and Experimental Physics of National Research Center “Kurchatov Institute”; National Research Nuclear University MEPhI (Moscow Engineering Physics Institute)
Russian Federation

Moscow, 117218;

Moscow, 115409



А. А. Nikitin
Kurchatov Complex for Theoretical and Experimental Physics of National Research Center “Kurchatov Institute”; National Research Nuclear University MEPhI (Moscow Engineering Physics Institute)
Russian Federation

Moscow, 117218;

Moscow, 115409



V. I. Lebedinsky
Scientific and Engineering Centre for Nuclear and Radiation Safety
Russian Federation

Moscow, 107140



V. B. Papina
National Research Center “Kurchatov Institute”
Russian Federation

Moscow, 123182



D. A. Zhurko
National Research Center “Kurchatov Institute”
Russian Federation

Moscow, 123182 



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For citations:


Kryukov А.М., Chernobaeva А.А., Erak D.Yu., Rogozhkin S.V., Nikitin А.А., Lebedinsky V.I., Papina V.B., Zhurko D.A. Analysis of Mechanical Properties and Nanostructure Changes of VVER-440 Reactor Pressure Vessel Metal after Annealing. Nuclear Physics and Engineering. 2021;12(5):255-269. (In Russ.) https://doi.org/10.56304/S2079562920060354

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ISSN 2079-5629 (Print)
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