Published August 31, 2008 | Version v1
Journal article

Oxidation of aluminum alloy cladding for research and test reactor fuel

  • 1. Argonne National Laboratory, Nuclear Engineering, 9700 South Cass Avenue, Argonne, IL 60439 (United States)
  • 2. Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID 83415-6188 (United States)

Description

The oxide thicknesses on aluminum alloy cladding were measured for the test plates from irradiation tests RERTR-6 and 7A in the ATR (advanced test reactor). The measured thicknesses were substantially lower than those of test plates with similar power from other reactors available in the literature. The main reason is believed to be due to the lower pH (pH 5.1-5.3) of the primary coolant water in the ATR than in the other reactors (pH 5.9-6.5) for which we have data. An empirical model for oxide film thickness predictions on aluminum alloy used as fuel cladding in the test reactors was developed as a function of irradiation time, temperature, surface heat flux, pH, and coolant flow rate. The applicable ranges of pH and coolant flow rates cover most research and test reactors. The predictions by the new model are in good agreement with the in-pile test data available in the literature as well as with the RERTR test data measured in the ATR

Availability note (English)

Available from http://dx.doi.org/10.1016/j.jnucmat.2008.06.032

Additional details

Identifiers

DOI
10.1016/j.jnucmat.2008.06.032;
PII
S0022-3115(08)00359-0;

Publishing Information

Journal Title
Journal of Nuclear Materials
Journal Volume
378
Journal Issue
2
Journal Page Range
p. 220-228
ISSN
0022-3115
CODEN
JNUMAM

Optional Information

Copyright
Copyright (c) 2008 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.