O.V. Ogorodnikova

Часть публикаций из профиля, по году от новых к старым. Это не полный список последних работ автора; работы без года — в конце.

• Characterization of plasma in the HiPIMS facility for simulation of fusion-oriented W co-deposition in He/H2 and He/D2 environments2025
• Release of ion-implanted 3He and D from tungsten under subsequent 4He ion irradiation2025
• Study of surface modification and deuterium retention in tugsten exposed to ELM-like pulsed deuterium plasma flows with noble gas impurities.2024
• Deuterium retention in tungsten pre-damaged by ELM-like high heat flux plasma and sequentially irradiated with deuterium ions2024
• Radiation-induced effects in self-passivating W-Cr-Y alloy2024
• Recent analysis of key plasma wall interactions issues for ITER2009
• Tritium inventory in ITER plasma-facing materials and tritium removal procedures2008 · аннотациясвернуть

  Interactions between the plasma and the vessel walls constitute a major engineering problem for next step fusion devices, such as ITER, determining the choice of the plasma-facing materials. A prominent issue in this…

• Ion-driven deuterium retention in tungsten2008 · аннотациясвернуть

  The ion-driven retention of deuterium in polycrystalline tungsten (PCW) is studied experimentally and theoretically as a function of temperature, incident ion energy, and ion fluence. Deuterium retention was…