Published June 1988 | Version v1
Report

Post-test examination and evaluation of the CORA experiments

  • 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

Optional Information

Notes
Imprint:Sicherheitsorientierte LWR-Forschung. Jahresbericht 1987.