Published April 1, 2017 | Version v1
Journal article

Microstructure studies of interdiffusion behavior of U3Si2/Zircaloy-4 at 800 and 1000 °C

Description

Fuel swelling during normal reactor operations could lead to unfavorable chemical interactions when in contact with its cladding. As new fuel types are developed, it is crucial to understand the interaction behavior between fuel and its cladding. Diffusion experiments between U3Si2 and Zricaloy-4 (Zry-4) were conducted at 800 and 1000 °C up to 100 h. The microstructure of pristine U3Si2 and U3Si2/Zry-4 interdiffusion products were examined using scanning electron microscopy (SEM) and transmission electron microscopy (TEM) equipped with an energy dispersive X-ray spectroscopy (EDS) system. The primary interdiffusion product observed at 800 °C is ZrSi2, with secondary phases of U-Zr in the Zry-4, and Fe-Cr-W-Zr-Si phases at Zry-4/ZrSi2 interface and Fe-Cr-U-Si phases at ZrSi2/U-Si interface. The primary interdiffusion products at 1000 °C were Zr2Si, U-Zr-Fe-Ni, U, U-Zr, and a low melting point phase U6Fe.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.jnucmat.2017.01.035

Additional details

Identifiers

DOI
10.1016/j.jnucmat.2017.01.035;
PII
S0022-3115(16)31111-4;

Publishing Information

Journal Title
Journal of Nuclear Materials
Journal Volume
486
Journal Page Range
p. 274-282
ISSN
0022-3115
CODEN
JNUMAM

Optional Information

Copyright
Copyright (c) 2017 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.