D. V. Kovalenko

TL;DR: In this paper, a brief overview on the disruption loads and mitigation strategies for ITER and the physics basis which is continuously refined through the current disruption R&D programs is discussed.

TL;DR: In this paper, an investigation of an erosion of the ITER-like divertor castellated targets of pure tungsten, lanthanum tengsten and CFC under plasma heat loads expected during the Type I ELMs and disruptions in ITER was carried out on a plasma gun QSPA-T at the SRC RF TRINITI under EU/RF collaboration.

TL;DR: In this article, experimental investigations of plasma facing components erosion under the plasma heat loads expected in ITER divertor during transient events such as the Type I Edge-Localized Modes and the disruptions were conducted.

TL;DR: In this article, ITER grade stainless steel (SS) 316L(N)-IG was tested in QSPA-T and JUDITH (electrons) under heat loads relevant to those expected from photon radiation on the ITER diagnostic first wall (DFW) during disruptions mitigated by massive gas injection.

TL;DR: In this article, a model was developed to describe the formation of wavy irregularities on the melted metal surface with allowance for the nonlinear stage of instability of the melted layer with a vapor/plasma flow above it.