Post-test examination and evaluation of the CORA experiments
Creators
- 1. Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Inst. fuer Material- und Festkoerperforschung 2 - Teilinstitut Huell- und Strukturmaterialien
Description
CORA-B and CORA-C out-of-pile experiments performed in the CORA test facility are reported. A bundle of 9 unheat and 16 electrically heated fuel rod simulators consisting of Zircaloy-4 cladding, annular alumina pellets, and central heater rod) had been submitted to a temperature-transient of roughly 20000C peak temperature. CORA-B was run under argon atmosphere but with a water-cooled lower bundle head, CORA-C was performed under steam. Both bundles showed comparable damage from steam oxidation, melting and chemical interaction of the metallographically prepared cross sections. Microstructures of Zircaloy-4 tube specimens from earlier high-temperature steam oxidation investigations are discussed. The oxide layer formation and the melting and cladding/scale interaction processes are presented in a sequence of microstructural examples. (orig./DG)
Additional details
Additional titles
- Original title (German)
- Nachuntersuchung und Auswertung der CORA-Experimente
Publishing Information
- Imprint Title
- Safety-oriented LWR research. Annual report 1987
- Imprint Pagination
- 319 p.
- Journal Page Range
- p. 63-81.
- Report number
- KFK--4450
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 19106351
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ALLOY-ZR98SN-4; FUEL ELEMENT CLUSTERS; FUEL-CLADDING INTERACTIONS; MELTDOWN; MICROSTRUCTURE; OXIDATION; PWR TYPE REACTORS; REACTOR SAFETY EXPERIMENTS; SIMULATION; STEAM; ULTRAHIGH TEMPERATURE
- Descriptors DEC
- ACCIDENTS; ALLOYS; CHEMICAL REACTIONS; CHROMIUM ADDITIONS; CORROSION RESISTANT ALLOYS; CRYSTAL STRUCTURE; ENRICHED URANIUM REACTORS; FUEL ASSEMBLIES; HEAT RESISTING ALLOYS; IRON ADDITIONS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; THERMAL REACTORS; TIN ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCALOY; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS
Optional Information
- Notes
- Imprint:Sicherheitsorientierte LWR-Forschung. Jahresbericht 1987.