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Analysis of Tin Diffusion in Zircaloy‐4 and Tin Redistribution after Steam Oxidation by Means of X‐ray Fluorescence Measurements
Author(s) -
Grosse Mirco,
Simon Rolf
Publication year - 2009
Publication title -
advanced engineering materials
Language(s) - English
Resource type - Journals
SCImago Journal Rank - 0.938
H-Index - 114
eISSN - 1527-2648
pISSN - 1438-1656
DOI - 10.1002/adem.200800344
Subject(s) - tin , materials science , zirconium alloy , cladding (metalworking) , zirconium , oxide , diffusion , metallurgy , tin oxide , atmospheric temperature range , analytical chemistry (journal) , chemistry , thermodynamics , physics , chromatography
The temperature dependence of tin diffusion coefficients in the nuclear fuel rod cladding tube material Zircaloy‐4 is determined in the range of 1 000–1 400 °C by means of X‐ray fluorescence measurements. During oxidation at these temperatures, tin is redistributed, as shown in the figure. Due to tin diffusion in zirconium being much slower than the growing of the oxide layer, tin is segregated inside the oxide layer and at phase boundaries.