Affiliation:
1. National University of Science and Technology “MISIS”, Leninsky Prospekt 4, 119049, Moscow, Russia
Abstract
AbstractHigh-temperature oxidation of E110 (Zr-1%Nb) zirconium alloy in steam at Т = 1100°C to various degrees has been carried out. Based on the studies of morphology and microstructure of the oxide film and metal, as well as on review of previously published results, the mechanism of alloy oxidation has been proposed, which includes oxide thickening close to the oxide/metal interface, growth of the thickened areas and their conversion into nodules, growth of the nodules and crowning of the metal surface (white spots), clustering of nodules under the formed oxide, formation of a double (white on the surface) oxide film and delamination of the oxide upper layer.
Subject
General Materials Science,General Chemical Engineering,General Chemistry
Reference62 articles.
1. High-temperature steam-oxidation behavior of Zr-1Nb cladding alloy E110;J Nucl Mater,2009
2. High temperature oxidation and residual ductility of fuel claddings from Zr-1Nb alloy having different contents of impurities;16th Int Symp: Zirconium in the Nuclear Industry, China,2010
3. Oxygen segregation in pre-hydrided zircaloy-4 cladding during a simulated LOCA transient;EPJ Nucl Sci Technol,2017
4. Oxygen segregation in pre-hydrided zircaloy-4 cladding during a simulated LOCA transient;EPJ Nucl Sci Technol,2017
5. On-going studies at CEA on chromium coated zirconium based nuclear fuel claddings for enhanced accident tolerant LWRS fuel. TopFuel, Switzerland,2015
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