Published April 15, 2016 | Version v1
Journal article

A new model of hydrogen redistribution in Zr alloy claddings during waterside corrosion in a temperature gradient

  • 1. Moscow Institute of Physics and Technology (MIPT), 9, Institutskii per., Dolgoprudny, Moscow Region, 141700 (Russian Federation)
  • 2. Nuclear Safety Institute (IBRAE), Russian Academy of Sciences, 52, B. Tulskaya, Moscow, 115191 (Russian Federation)

Description

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. - Highlights: • A new model for Zr alloys hydriding during waterside corrosion is developed. • The model is based on consideration of mass transfer through the two-phase region. • The model is applied to analysis of and in-reactor and autoclave experiments.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.jnucmat.2016.01.032

Additional details

Identifiers

DOI
10.1016/j.jnucmat.2016.01.032;
PII
S0022-3115(16)30034-4;

Publishing Information

Journal Title
Journal of Nuclear Materials
Journal Volume
472
Journal Page Range
p. 65-75
ISSN
0022-3115
CODEN
JNUMAM

Optional Information

Copyright
Copyright (c) 2016 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.