Simulated Irradiation of 16Cr–4Al–2W–0.3Ti–0.3Y2O3ODS Steel Promising for Fusion Reactors in Vikhr Plasma Focus Facility

Autor: Demina, E. V., Vinogradova, N. A., Demin, A. S., Epifanov, N. A., Morozov, E. V., Mikhailova, A. B., Pimenov, V. N., Prusakova, M. D., Rogozhkin, S. V., Shevtsov, S. V.
Zdroj: Inorganic Materials: Applied Research; April 2023, Vol. 14 Issue: 2 p310-316, 7p
Abstrakt: Abstract: This article discusses radiation thermal resistance of 16Cr–4Al–2W–0.3Ti–0.3Y2O3oxide dispersion strengthened (ODS) ferritic steel promising for application in nuclear fusion facilities under the impact of intense pulsed flows of helium ions and helium plasma using Vikhr Plasma Focus facility. The power density of high velocity helium ions and flows of high temperature helium plasma was ~108and 107W/cm2at the impact duration of ~50 and 100 ns, respectively. The number of impact pulses Nwas varied in the range from 10 to 30. The rate of radiative sputtering varied slightly with increase in the number of impact pulses of energy flow on material and amounted to h≈ 0.01–0.02 μm/pulse. The irradiated surface after repeated melting under the action of pulsed radiation thermal load by intense energy flows acquired a wavelike pattern with inclusion of disperse microparticles of the second phase containing mainly yttrium, oxygen, aluminum, iron, and titanium. At the same time, in contrast to the refractory metals (W, Mo, Ti) previously studied under the same conditions, no micro- and macrocracks were formed on the surface facing plasma. The Vikhr Plasma Focus facility has proven to be an efficient tool for simulation tests of candidate materials of fusion reactors with magnetic and inertial plasma confinement.
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