State-of-the-art of the Russian works on selection and certification of structural materials for the first wall, blanket and divertor of fusion reactor (ITER project)

Autor:	N. V. Odintsov, Yu. M. Trapeznikov, Yu. G. Strebkov, V. A. Glukhikh, I. V. Gorynin, Yu. G. Prokofjev, G. Kalinin, V. V. Rybin, V. F. Vinokurov, V. G. Markov
Rok vydání:	1994
Předmět:	Austenite Yield (engineering) Materials science Structural material Nuclear Energy and Engineering Neutron flux Divertor Nuclear engineering Fusion power Blanket Condensed Matter Physics Ductility
Zdroj:	Plasma Devices and Operations. 3:1-21
ISSN:	1029-4929 1051-9998
DOI:	10.1080/10519999408201799
Popis:	The basic structural materials for the ITER are considered. They are austenitic stainless steels for the first wall and blanket and alloys on the base of Mo and Cu for the divertor. The basic mechanical properties in the initial state and the influence of irradiation on them are presented. The mechanical and sone other properties of 0.04C-16Cr-11Ni-3Mo-0,5Ti steel do not yield to foreign analogs and exceed them by some parameters.
Databáze:	OpenAIRE
Externí odkaz:	https://explore.openaire.eu/search/publication?articleId=doi_________::cd9a43712c3a9f4a8a069f130a64dc89 https://doi.org/10.1080/10519999408201799 Zobrazit plný text záznamu