A new model of hydrogen redistribution in Zr alloy claddings during waterside corrosion in a temperature gradient
Abstract
A new model for hydrogen spatial redistribution and hydride precipitation in Zr alloys during waterside corrosion extends the traditional approach, valid for consideration of a relatively low volume fraction of the precipitated hydride phase, to a more general case of heavily precipitated hydrides typical for high-burnup fuel cladding tubes of pressurized water reactors and also observed in various autoclave corrosion tests with high hydrogen supercharging. Being implemented in the SVECHA/QUENCH (S/Q) code, the new model reasonably explains various observations in corrosion tests at constant temperature and under temperature gradient as well as under in-reactor corrosion conditions.
- Publication:
-
Journal of Nuclear Materials
- Pub Date:
- April 2016
- DOI:
- 10.1016/j.jnucmat.2016.01.032
- Bibcode:
- 2016JNuM..472...65V
- Keywords:
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- Zr alloy cladding corrosion;
- Hydrogen supercharging;
- Outer hydride rim