Published April 2008
| Version v1
Report
Behaviour of oxide layer of zirconium-based fuel rod cladding under steam starvation conditions
Description
This report presents the results of tests relating to the long-term annealing of preoxidised Zircaloy cladding tubes in an inert atmosphere at annealing temperatures between 1250 and 1500 C and a corresponding model. The tests were aimed at investigating the reduction kinetics of the oxide layer in the steam starvation phase by the progression of core drying during a severe accident. Homogeneous formation of α-Zr(O) precipitations inside the oxide layer and formation of α-Zr(O) scale on the outer cladding surface were detected in addition to a decrease in the oxide layer thickness. This phenomenon is supposed to have a strong influence on intensive hydrogen release during the following quench phase. (orig.)
Availability note (English)
Available from TIB Hannover: ZA 5141(7373)Additional details
Publishing Information
- Imprint Pagination
- 70 p.
- ISSN
- 0947-8620
- Report number
- FZKA--7373
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 39093542
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- ANNEALING; FUEL CANS; HYDROGEN; INERT ATMOSPHERE; LAYERS; PRECIPITATION; QUENCHING; REACTOR ACCIDENTS; STEAM; SURFACES; THICKNESS; TUBES; ZIRCALOY; ZIRCONIUM OXIDES
- Descriptors DEC
- ACCIDENTS; ALLOYS; ATMOSPHERES; CHALCOGENIDES; CONTROLLED ATMOSPHERES; DIMENSIONS; ELEMENTS; HEAT TREATMENTS; NONMETALS; OXIDES; OXYGEN COMPOUNDS; SEPARATION PROCESSES; TRANSITION ELEMENT ALLOYS; TRANSITION ELEMENT COMPOUNDS; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS; ZIRCONIUM COMPOUNDS