Aleev, A.

Bogachev, A.

Chalykh, B.

Golubev, A. A.

Kuibeda, R.

Kulevoy, T.

Möslang, A.

Nikitin, A.

Orlov, N.

Rogozhkin, S.

Vladimirov, P.

Zaluzhnyi, A.

English

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«Effect of Heavy-lon lrradiation on the Nanoscale State of Advanced Reactor Ferritic-Martensitic Steels»                          Irradiation experiment Investigated materials Statistical analysis of the oxide particles in the materials before and after irradiation Summary Change of nanohardness between irradiated and initial states • The study of the microstructure of the initial and ion irradiated samples of EK-181, ODS Eurofer, ODS 13.5%Cr and ODS 13.5%Cr-0.3%Ti steels have been carried out. Samples have been irradiated by ions Fe2+, Ti 2+ with energy 5.6 MeV, 4.9 MeV respectively and by ions Ti 2+ and  N+ with energy 150 keV, 60 keV respectively. • In all irradiated materials observed increased number density of dislocation defects in the region of maximum damage. Highest value has been found in materials irradiated by high-energy ions ~ 1012 def./cm2. • Impact of ions on oxide inclusions reduces the proportion of large (> 20 nm) particles and increasing the total number density of  oxides. • The highest value of hardening (~ 10%) was found out for EK-181 steel irradiated by Ti2+, and sequential irradiated by Ti2+, and then N+ (~20%).  Microstructure of materials after ion irradiation Introduction Oxide Dispersion Strengthened (ODS) ferritic–martensitic steels are considered for nuclear applications as structural components for fusion or fission reactors. To ensure good performance in service, the microstructure of such ODS steels have to remain stable under irradiation at high temperature. Oxide dispersion strengthened F/M steels have been developed using the addition of nanoscale oxide particles to increase the high-temperature strength. These nano-oxides act as pinning points for dislocations, improving creep strength. Additionally, the nano-precipitates are expected to promote recombination of irradiation-produced point defects. Since the nanoparticles are believed critical to the high temperature strength and potential radiation resistance, the long-term stability of the nanoparticles under irradiation is an important issue.  The main purpose of this work was to investigate the processes of evolution of oxide particles in ODS perspective steels under heavy ions irradiation to simulate neutron damage.  1 Ions: Ti2+ 150 keV; N+  60 keV Ions: Ti2+ 4,9 MeV;  Fe2+ 5,6 MeV SRIM simulation of irradiation iron by ions Parameters of irradiaton:  Fluence: 1015 ions/cm2;  Temperature: 300 К; Ions: Ti2+ - 4.9 MeV; Fe2+ - 5.6 Mev; Ti2+ - 150 keV; N+ - 60 keV The TEM samples preparation technique that forms a thin foil at a predetermined depth in ion irradiated material has been worked out. Changes in size distribution of oxide particles Mean size, nm Number density, m-3 A. Bogachev1,2, S. Rogozhkin1,2, A. Aleev1,2, B. Chalykh1,2, T. Kulevoy1,2, R. Kuibeda1, A. Nikitin1,2, N. Orlov1,2, A. Zaluzhnyi1,2, A.A. Golubev1,2, P. Vladimirov3,  A. Möslang3 1SSC RF – ITEP, Moscow, Russia, 2 National Research Nuclear University «MEPhI», Moscow, Russia, 3 KIT (IAM-AWP), Karlsruhe, Germany Ion irradiation leads to decrease of the mean size and to increase of the number density of oxide particles due to the formation of small (<5 nm) oxide Shift of distribution to less sizes 1 1 Composition, at.% Cr Ti Y O V Oxides Clusters Mean size, nm Number density, m-3  Size, nm Number density, m-3 ODS Eurofer 9.65 - 0.25 0.37 0.38 6 2∙1021 ~ 2-4 ~ 1024 ODS 13.5%Cr 14.60 - 0.15 0.22 - 14 1020 ~ 2-4 ~ 1023 ODS 13.5%Cr-0.3%Ti 14.60 0.35 0.15 0.22 - 8 2∙1021 ~ 2-4 ~ 1024 Pinning of dislocation 100 nm Number density of dislocation loops (cm-2) Material Initial Fe Ti N EK-181  (low energy) 108 - 1010 <1010 ODS Eurofer  (low energy) - 7·109 3·109 ODS 13.5%Cr 1012 1012 - ODS 13.5%Cr-0.3%Ti 1012 1012 Composition,  аt.% Cr V Mn Si C N Clusters Size, nm Number density, m-3 EK-181 11,9 0,31 0,95 0,73 0,64 0,16 ~ 2-4 ~ 1024 Heavy ion irradiation facility 27 MHz RFQ accelerator Type 111 100 nm Type 100 doped layer layer of maximum damage High density of dislocation defects ODS 13.5%Cr irr. Fe2+  irr. Ti2+  Depth of indentation  ODS 13.5%Cr-0.3%Ti irr. Fe2+  irr. Ti2+  Depth of indentation  Depth of indentation  Depth of indentation  Depth of indentation  Depth of indentation  EK-181 irr. N+                                    EK-181 irr. Ti2+ EK-181 irr. N+ + Ti2+                                EK-181 irr. Ti2+ + N+ ODS Eurofer irr. N+                                    ODS Eurofer irr. Ti2+ ODS Eurofer irr. N+ + Ti2+                   ODS Eurofer irr. Ti2+ + N+  

Effect of heavy-ion irradiation on the nanoscale state of advanced reactor ferritic-martensitic steels

https://publikationen.bibliothek.kit.edu/220101316/3816852

Effect of heavy-ion irradiation on the nanoscale state of advanced reactor ferritic-martensitic steels

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