V.P. Shestakov

TL;DR: In this paper, the authors showed that beryllium intermetallic compounds had excellent property and the feasibility as the neutron multiplier for fusion DEMO blanket, and fabrication technology for the pebbles was studied.

TL;DR: In this article, a series of hydrogen and deuterium permeation experiments was performed for ferritic F82H steel with and without a ceramic coating of Cr2O3-SiO2 including CrPO4.

TL;DR: In this article, some pebbles of modified Be 12-Ti that included the Be phase were obtained by the rotating electrode method, and preliminary experiments indicated that compatibility with stainless steel and tritium breeder materials, deuterium release, natural oxidation and oxidations by steam interaction were better than the behavior of beryllium.

TL;DR: In this article, the main issues related to the use of Be in a fusion reactor as both neutron multiplier and first wall material are discussed, including potential reactions with steam during accidents and the health and environmental aspects of its use, reprocessing and reuse, or disposal.

TL;DR: The most recent workshop on beryllium technology for fusion was held in Karlsruhe, Germany on 15-17 September 1999 as mentioned in this paper, and a summary of the findings presented there and their implications for the use of the material in the development of fusion reactors are presented.