Published August 1991 | Version v1
Journal article Metadata-only

A model for waterside oxidation of Zircaloy fuel cladding in pressurized water reactors

Creators

  • 1. Institute of Atomic Energy Research, Riyadh (Saudi Arabia)
  • 2. Oregon State Univ., Corvallis (USA). Dept. of Nuclear Engineering

Description

A model is developed to simulate the oxidation of Zircaloy fuel rod cladding exposed to pressurized water reactor operating conditions. The model is used to predict the oxidation rate for both ex- and in-reactor conditions in terms of the weight gain and oxide thickness. Comparisons of the model predictions with experimental data show very good agreement. (orig.)

Additional details

Publishing Information

Journal Title
Journal of Nuclear Materials
Journal Volume
183
Journal Issue
3
Series
J. Nucl. Mater.
Journal Page Range
186-194
ISSN
0022-3115
CODEN
JNUMA

INIS

Country of Publication
Netherlands
Country of Input or Organization
Netherlands
INIS RN
22088540
Subject category
S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
ALLOY-ZR98SN-4; FUEL CANS; FUEL RODS; MATHEMATICAL MODELS; OXIDATION; PWR TYPE REACTORS; SIMULATION; WATER
Descriptors DEC
ALLOYS; CHEMICAL REACTIONS; CHROMIUM ADDITIONS; CORROSION RESISTANT ALLOYS; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; HEAT RESISTING ALLOYS; HYDROGEN COMPOUNDS; IRON ADDITIONS; OXYGEN COMPOUNDS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; TIN ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCALOY; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS