Thermochemical embrittlement of the zirconium cladding of a fuel rod and oxidative recrystallization of the fuel material in the course of spent nuclear fuel reprocessing
Crossref DOI link: https://doi.org/10.1134/S1066362215010154
Published Online: 2015-02-17
Published Print: 2015-01
Update policy: https://doi.org/10.1007/springer_crossmark_policy
Metalidi, M. M.
Shapovalov, S. V.
Ismailov, R. V.
Skriplev, M. I.
Beznosyuk, V. I.
Fedorov, Yu. S.
Text and Data Mining valid from 2015-01-01