Title: Behavior of Modified Zirconium-Alloy Fuel-Element Cladding Under Irradiation.
Authors: Kulakov, G. V.; Konovalov, Yu. V.; Kosaurov, A. A.; Peregud, M. M.; Nikulina, A. B.; Shishin, V. Yu.; Ovchinnikov, V. A.; Shel’dyakov, A. A.
Abstract: The first reactor tests and post-reactor studies of fuel elements with cladding made from the zirconium alloys E-636M, E-635opt, and E-635M1, developed at VNIINM, have been conducted. The purpose of the studies was to search for alloys of the type E-635 that surpass the base alloy in terms of resistance to corrosion and hydration. The studies make it possible to recommend the alloys E-635M and E-635opt for use as cladding of the fuel elements in extended-life cores.
Subjects: ZIRCONIUM alloys; NUCLEAR fuel claddings; IRRADIATION; CORROSION prevention; HYDRATION
Publication: Atomic Energy, 2018, Vol 123, Issue 6, p399
ISSN: 1063-4258
Publication type: Academic Journal
DOI: 10.1007/s10512-018-0359-8

Behavior of Modified Zirconium-Alloy Fuel-Element Cladding Under Irradiation.

Kulakov, G. V.; Konovalov, Yu. V.; Kosaurov, A. A.; Peregud, M. M.; Nikulina, A. B.; Shishin, V. Yu.; Ovchinnikov, V. A.; Shel’dyakov, A. A.