Published November 1991
| Version v1
Journal article
Simulation with the HITO code of the interaction of Zircaloy with uranium dioxide and steam at high temperatures
Creators
- 1. Dept. Materiales, Comision Nacional de Energia Atomica, Buenos Aires (Argentina)
Description
In a hypothetical severe fuel damage accident the Zircaloy (Zry) cladding may react, on its internal face, with the UO2 fuel and, on the external face, with steam. These reactions result in the formation of ZrO2, various oxygen stabilized α-Zr(O) phases and a (U, Zr) alloy. The HITO (High Temperature Oxidation) code describes both internal and external oxidation of the Zry cladding. The diffusion equations of oxygen in the various reaction layers are solved by an implicit finite differences method. Experimental results of isothermal and transient experiments are used to check the code. Comparison between the experimental data and the results calculated with the HITO code shows a good agreement. (orig.)
Additional details
Publishing Information
- Journal Title
- Journal of Nuclear Materials
- Journal Volume
- 185
- Journal Issue
- 1
- Series
- J. Nucl. Mater.
- Journal Page Range
- 96-113
- ISSN
- 0022-3115
- CODEN
- JNUMA
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 23027467
- Subject category
- S36: MATERIALS SCIENCE; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- COMPARATIVE EVALUATIONS; EQUATIONS; FUEL CANS; FUEL-CLADDING INTERACTIONS; MATHEMATICAL MODELS; OXIDATION; SIMULATION; STEAM; TEMPERATURE RANGE 1000-4000 K; URANIUM DIOXIDE; WATER VAPOR; ZIRCALOY; ZIRCONIUM OXIDES
- Descriptors DEC
- ACTINIDE COMPOUNDS; ALLOYS; CHALCOGENIDES; CHEMICAL REACTIONS; EVALUATION; FLUIDS; GASES; OXIDES; OXYGEN COMPOUNDS; TEMPERATURE RANGE; TRANSITION ELEMENT COMPOUNDS; URANIUM COMPOUNDS; URANIUM OXIDES; VAPORS; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS; ZIRCONIUM COMPOUNDS