Published August 1988 | Version v1
Journal article

Transient oxidation of Zircaloy fuel cladding in high temperature steam

  • 1. National Tsing Hua Univ., Hsinchu (Taiwan). Dept. of Nuclear Engineering

Description

Reactor grade Zircaloy-4 specimens were subjected to a temperature transient of different heating rates as well as to isothermal heating in flowing steam. Both electrical internal heating and external heating by infrared radiation were used. Following each test the oxide layer and the stabilized α-layer thicknesses, using metallographic examination, were obtained as a measure of corrosion rates. The measured oxide thickness above heating rates of 30C/s are found to deviate from the parabolic rate law by this experimental study. The comparison between fitted parameters from earlier studies will be discussed for both transient and isothermal measurements. (orig.)

Additional details

Publishing Information

Journal Title
Journal of Nuclear Materials
Journal Volume
158
Series
J. Nucl. Mater.
Journal Page Range
217-223
ISSN
0022-3115
CODEN
JNUMA

Optional Information

Contract/Grant/Project number
Contract NSC-73-0413-E007-06