Open AccessDevelopment of new cladding types for nuclear fuel
Author(s) -
Zoltán Hózer,
T. Novotny,
Erzsébet Perez-Feró,
Márta Horváth,
A. Pintér Csordás,
Péter Szabó,
Levente Illés,
M. Schyns,
Rémi Delville,
D Kim,
W J Kim,
Martin Ševeček
Publication year - 2020
Publication title -
iop conference series. materials science and engineering
Language(s) - English
Resource type - Journals
eISSN - 1757-899X
pISSN - 1757-8981
DOI - 10.1088/1757-899x/903/1/012004
Subject(s) - cladding (metalworking) , materials science , alloy , nuclear fuel , hydrogen , metallurgy , microstructure , pressurized water reactor , nuclear reactor , helium , nuclear engineering , composite material , nuclear chemistry , chemistry , organic chemistry , engineering
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 SiC f /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.