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

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

doi:10.1007/s10512-018-0359-8

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

Authors: Kulakov G.V.¹, Konovalov Y.V.¹, Kosaurov A.A.¹, Peregud M.M.¹, Nikulina A.B.¹, Shishin V.Y.², Ovchinnikov V.A.², Shel’dyakov A.A.²
Affiliations:
1. Bochvar High-Technology Research Institute for Inorganic Materials (VNIINM)
2. State Science Center – Research Institute for Atomic Reactors (GNTs NIIAR)
Issue: Vol 123, No 6 (2018)
Pages: 399-405
Section: Article
URL: https://journals.rcsi.science/1063-4258/article/view/248843
DOI: https://doi.org/10.1007/s10512-018-0359-8
ID: 248843

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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.