@inproceedings{4295140fd95541a88441058ab48a5c4d,
title = "Development of new cladding types for nuclear fuel: IOP Conference Series: Materials Science and Engineering",
abstract = "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.",
keywords = "Cladding, Coating, Chromium, Oxidation",
author = "Zolt{\'a}n H{\'o}zer and T. Novotny and E. Perez-Fer{\'o} and M. Horv{\'a}th and P. Szab{\'o} and L. Ill{\'e}s and Marc Schyns and R{\'e}mi Delville and D. Kim and M. Sevecek",
note = "Score=3",
year = "2020",
month = dec,
day = "4",
doi = "10.1088/1757-899X/903/1/012004",
language = "English",
volume = "903",
series = "IOP Conference Series: Materials Science and Engineering",
publisher = "IOP Publishing Ltd",
pages = "1--9",
booktitle = "IOP Conference Series: Materials Science and Engineering",
}