Published August 1988
| Version v1
Journal article
Transient oxidation of Zircaloy fuel cladding in high temperature steam
Creators
- 1. National Tsing Hua Univ., Hsinchu (Taiwan). Dept. of Nuclear Engineering
Description
Reactor grade Zircaloy-4 specimens were subjected to a temperature transient of different heating rates as well as to isothermal heating in flowing steam. Both electrical internal heating and external heating by infrared radiation were used. Following each test the oxide layer and the stabilized α-layer thicknesses, using metallographic examination, were obtained as a measure of corrosion rates. The measured oxide thickness above heating rates of 30C/s are found to deviate from the parabolic rate law by this experimental study. The comparison between fitted parameters from earlier studies will be discussed for both transient and isothermal measurements. (orig.)
Additional details
Publishing Information
- Journal Title
- Journal of Nuclear Materials
- Journal Volume
- 158
- Series
- J. Nucl. Mater.
- Journal Page Range
- 217-223
- ISSN
- 0022-3115
- CODEN
- JNUMA
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 20001900
- Subject category
- S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ALLOY-ZR98SN-4; CORROSION; FUEL CANS; HEATING RATE; LAYERS; MICROSTRUCTURE; OXIDATION; STEAM; THICKNESS; TRANSIENTS; VERY HIGH TEMPERATURE; ZIRCONIUM OXIDES; ZIRCONIUM-ALPHA
- Descriptors DEC
- ALLOYS; CHALCOGENIDES; CHEMICAL REACTIONS; CHROMIUM ADDITIONS; CORROSION RESISTANT ALLOYS; CRYSTAL STRUCTURE; DIMENSIONS; ELEMENTS; HEAT RESISTING ALLOYS; IRON ADDITIONS; METALS; OXIDES; OXYGEN COMPOUNDS; TIN ALLOYS; TRANSITION ELEMENT COMPOUNDS; TRANSITION ELEMENTS; ZIRCALOY; ZIRCONIUM; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS; ZIRCONIUM COMPOUNDS
Optional Information
- Contract/Grant/Project number
- Contract NSC-73-0413-E007-06