Properties of neutron irradiated carbon-based materials for fusion reactor application

Autor:	A. A. Mitrofanskii, Burtseva Tatyana A, P. A. Platonov, O. K. Chugunov, E. F. Dovguchits, M. I. Persin, S. I. Alekseev, V. A. Socolov, V. M. Alekseev, E. I. Trofimchuk, V. I. Karpukhin
Rok vydání:	1994
Předmět:	Thermal shock Materials science Nuclear Energy and Engineering Neutron flux Astrophysics::High Energy Astrophysical Phenomena Divertor Neutron Fusion power Composite material Condensed Matter Physics Neutron moderator Neutron temperature Neutron activation
Zdroj:	Plasma Devices and Operations. 3:79-92
ISSN:	1029-4929 1051-9998
DOI:	10.1080/10519999408201804
Popis:	Carbon-based materials are widely used for fusion reactor plasma facing components. They are characterized by a low atomic number, fair thermophysical characteristics thermal shock resistance and low neutron activation. Ignition machines such as ITER will produce high neutron fluxes and influence of neutron damage on different properties of graphites and carbon-carbon composites must be evaluated. Irradiation was performed in the Kurchatov Institute IR-8 reactor, where a 0.18 Mev neutron flux intensity reacted 1–3•1013 1/cm2•s. A peak neutron fluence of 2.6•1020 1/cm2, at temperature up to 650°C. The recrystallized graphites and four- and five- directional carbon-carbon composites were irradiated. Thermal conductivity, dimensional changes, strength and coefficient of thermal expansion are reported for the materials examined.
Databáze:	OpenAIRE
Externí odkaz:	https://explore.openaire.eu/search/publication?articleId=doi_________::daebb675a274e6b0f5f5c74c61782996 https://doi.org/10.1080/10519999408201804 Zobrazit plný text záznamu