Development of new cladding types for nuclear fuel

Autor:	A. Pintér Csordás, M Schyns, T. Novotny, W.-J. Kim, Péter Szabó, L Illés, R Delville, E. Perez-Feró, M. Horváth, Martin Ševeček, D Kim, Zoltán Hózer
Rok vydání:	2020
Předmět:	Materials science Nuclear fuel Metallurgy Alloy chemistry.chemical_element engineering.material Cladding (fiber optics) Microstructure chemistry Impurity engineering Tube (fluid conveyance) Helium Hydrogen production
Zdroj:	IOP Conference Series: Materials Science and Engineering. 903:012004
ISSN:	1757-899X 1757-8981
DOI:	10.1088/1757-899x/903/1/012004
Popis:	Three different cladding types were tested for nuclear fuel in traditional light water reactors and generation IV gas-cooled fast reactors. Cr coated Zr cladding was tested in steam atmosphere up to 1200 °C to demonstrate moderate oxidation and hydrogen production in accident conditions. 15-15Ti stainless steel alloy and SiCf/SiC cladding tube samples were treated in helium atmosphere with different impurities for several hours at 1000 °C. Additional mechanical testing and microstructure examinations were carried out with as-received samples and with specimens after high temperature treatments. The experiments results indicated the applicability of the tested materials for reactor conditions in the investigated range of parameters.
Databáze:	OpenAIRE
Externí odkaz:	https://explore.openaire.eu/search/publication?articleId=doi_________::69c5967173cdc79bd76cfac8bcbd098d https://doi.org/10.1088/1757-899x/903/1/012004 Zobrazit plný text záznamu