S.V. Fedotova
Kurchatov Institute
Network
Latest external collaboration on country level. Dive into details by clicking on the dots.
Publication
Featured researches published by S.V. Fedotova.
Key Engineering Materials | 2013
B.A. Gurovich; E.A. Kuleshova; D.A. Maltsev; O. Zabusov; K.E. Prikhodko; A.S. Frolov; S.V. Fedotova; D. Erak; Zhurko Denis; Mikhail Saltykov
In this paper the influence of fast neutron flux on the structural features and properties of VVER-1000 reactor pressure vessel steels was studied. It is shown that for high Ni steels the flux effect is due to hardening and non-hardening mechanisms of radiation embrittlement.
Microscopy and Microanalysis | 2016
Emmanuelle A. Marquis; Vicente J. Araullo-Peters; Aurianne Etienne; S.V. Fedotova; Katsuhiko Fujii; Koji Fukuya; E.A. Kuleshova; Anabelle Legrand; Andrew London; Sergio Lozano-Perez; Yasuyoshi Nagai; Kenji Nishida; B. Radiguet; Daniel K. Schreiber; Naoki Soneda; Mattias Thuvander; Takeshi Toyama; Faiza Sefta; Peter Chou
1. Department of Materials Science and Engineering, University of Michigan, Ann Arbor, MI, U.S.A. 2. Groupe de Physique des Matériaux, UMR CNRS 6634, Université de Rouen, Saint Etienne du Rouvray Cedex, France 4. NRC “Kurchatov Institute”, Moscow, Russia 3. Institute of Nuclear Safety System, Inc., Kyoto, Japan 5. Commissariat à l’Energie Atomique (CEA), Saclay, France 6. Department of Materials, University of Oxford, U.K. 7. Institute for Materials Research, Tohoku University, Oarai Japan 8. Materials Science Research Laboratory, Central Research Institute of Electric Power Industry, Nagasaka, Japan 9. Energy and Environment Directorate, Pacific Northwest National Laboratory, Richland, WA, U.S.A. 10. Department of Physics, Chalmers University of Technology, Chalmers, Sweden 11. Departement Métallurgie, EDF, Moret sur Loing, France 12. Electric Power Research Institute, Palo Alto, CA, U.S.A.
Key Engineering Materials | 2013
O. Zabusov; B.A. Gurovich; E.A. Kuleshova; Michail A. Saltykov; S.V. Fedotova; Alexey P. Dementjev
Service life of VVER-type nuclear reactor is limited by decrease in brittle fracture resistance of reactor pressure vessel produced of low-alloy low-carbon steel under effect of irradiation and/or elevated temperatures. In this work fracture surfaces were studied by Auger-electron spectroscopy in order to estimate the contribution of intergranular embrittlement to the degradation of reactor pressure vessel steels under the influence of operating conditions. It was demonstrated that irradiation induced segregation leads to an increase of P content in grain boundaries that promotes intergranular brittle fracture on fracture surfaces. The similar effect but to a lesser degree was shown in the case of long-term temperature exposure. The grain boundary structure was examined and an effect of carbides located on the grain boundaries is supposed due to increased phosphorus segregation on carbide/matrix interface boundaries.
18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, 2017, Portland | 2018
Emmanuelle A. Marquis; Vicente J. Araullo-Peters; Yan Dong; Auriane Etienne; S.V. Fedotova; Katsuhiko Fujii; Koji Fukuya; E.A. Kuleshova; Anabelle Lopez; Andrew London; Sergio Lozano-Perez; Yasuyoshi Nagai; Kenji Nishida; B. Radiguet; Daniel K. Schreiber; Naoki Soneda; Mattias Thuvander; T. Toyama; Faiza Sefta; Peter Chou
Because atom probe tomography (APT) provides three-dimensional reconstructions of small volumes by resolving atomic chemical identities and positions, it is uniquely suited to analyze solute clustering phenomena in materials. A number of approaches have been developed to extract clustering information from the 3D reconstructed dataset, and numerous reports can be found applying these methods to a wide variety of materials questions. However, results from clustering analyses can differ significantly from one report to another, even when performed on similar microstructures, raising questions about the reliability of APT to quantitatively describe solute clustering. In addition, analysis details are often not provided, preventing independent confirmation of the results. With the number of APT research groups growing quickly, the APT community recognizes the need for educating new users about common methods and artefacts, and for developing analysis and data reporting protocols that address issues of reproducibility, errors, and variability. To this end, a round robin experiment was organized among ten different international institutions. The goal is to provide a consistent framework for the analysis of irradiated stainless steels using APT. Through the development of more reliable and reproducible data analysis and through communication, this project also aims to advance the understanding between irradiated microstructure and materials performance by providing more complete quantitative microstructural input for modeling. The results, methods, and findings of this round robin will also apply to other clustering phenomena studied using APT, beyond the theme of radiation damage.
Journal of Nuclear Materials | 2013
B.A. Gurovich; E.A. Kuleshova; O. Zabusov; S.V. Fedotova; A.S. Frolov; Michail A. Saltykov; D.A. Maltsev
Journal of Nuclear Materials | 2014
Yaroslav I. Shtrombakh; B.A. Gurovich; E.A. Kuleshova; D.A. Maltsev; S.V. Fedotova; A.A. Chernobaeva
Journal of Nuclear Materials | 2013
B.A. Gurovich; E.A. Kuleshova; Ya. I. Shtrombakh; S.V. Fedotova; O. Zabusov; K.E. Prikhodko; D.A. Zhurko
Journal of Nuclear Materials | 2015
B.A. Gurovich; E.A. Kuleshova; Ya. I. Shtrombakh; S.V. Fedotova; D.A. Maltsev; A.S. Frolov; O. Zabusov; D. Erak; D.A. Zhurko
Journal of Nuclear Materials | 2016
E.A. Kuleshova; B.A. Gurovich; Z.V. Lavrukhina; Michail A. Saltykov; S.V. Fedotova; A.N. Khodan
Journal of Nuclear Materials | 2015
Ya. I. Shtrombakh; B.A. Gurovich; E.A. Kuleshova; A.S. Frolov; S.V. Fedotova; D.A. Zhurko; E.V. Krikun