Ogorodnikova Olga V.

Showing publications for last 3 years

1. Article
   Web of Science & Scopus
   Characterization of plasma in the HiPIMS facility for simulation of fusion-oriented W co-deposition in He/H2 and He/D2 environments // Journal of Nuclear Materials, 2025 Vol. 607, Q1 doi
2. Article
   Web of Science & Scopus
   Release of ion-implanted 3He and D from tungsten under subsequent 4He ion irradiation // Journal of Nuclear Materials, 2025 Vol. 606, Q1 doi
3. Article
   Web of Science & Scopus
   Deuterium retention in tungsten pre-damaged by ELM-like high heat flux plasma and sequentially irradiated with deuterium ions // International Journal of Hydrogen Energy, 2024 Vol. 92, TOP10 pp. 821-827 doi
4. Article
   Web of Science & Scopus
   Radiation-induced effects in self-passivating W-Cr-Y alloy // Journal of Nuclear Materials, 2024 Vol. 595, Q1 doi
5. Article
   Web of Science & Scopus
   Annealing effect on deuterium retention in W-Cr-Y alloy // Journal of Nuclear Materials, 2024 Vol. 593, Q1 doi
6. Article
   Web of Science & Scopus
   Microstructure and Mechanical Properties of W–10Cr–0.5Y Alloy under Heavy Ion Irradiation // Physics of Atomic Nuclei, 2023 Vol. 86, No. 12, Q4 pp. 2618-2627 doi
7. RSCI SIMULATION OF RADIATION DRIVEN PROCESSES IN TUNGSTEN ALLOYS USING ION IRRADIATIONSIMULATION OF RADIATION DRIVEN PROCESSES IN TUNGSTEN ALLOYS USING ION IRRADIATION // 2023 pp. 65-67
8. Article
   Web of Science & Scopus
   MAGNETRON SPUTTER DEPOSITION OF TUNGSTEN COATINGS IN DEUTERIUM–HELIUM MIXTURES // High Temperature Material Processes, 2023 Vol. 27, No. 4, Q3 pp. 25-32 doi
9. RSCI SIMULATION OF RADIATION DAMAGE IN W-10Cr TUNGSTEN ALLOY USING ION BEAMSSIMULATION OF RADIATION DAMAGE IN W-10Cr TUNGSTEN ALLOY USING ION BEAMS // 2023 pp. 291
10. Article
    Web of Science & Scopus
    Deuterium retention in W-Cr-Y alloy: Impact of the manufacturing method and helium presence // Journal of Nuclear Materials, 2023 Vol. 578, Q1 doi
11. Article
    Web of Science & Scopus
    Helium and deuterium retention in Eurofer97 under sequential irradiation at low fluxes // Journal of Nuclear Materials, 2022 Vol. 568, Q1 doi
12. Article
    Web of Science & Scopus
    Tungsten fuzz annealing effect on deuterium retention in polycrystalline tungsten // Journal of Nuclear Materials, 2022 Vol. 567, Q1 doi
13. Article
    Web of Science & Scopus
    Deuterium and helium retention and corresponding modifications of W under heat loads relevant to ITER transient plasma events: Part I. The power load below the tungsten melting temperature // Journal of Nuclear Materials, 2022 Vol. 558, Q1 doi

Showing conferences for last 3 years