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Separate-effects tests on the investigation of high-temperature oxidation behavior and mechanical properties of Zircaloy-2 to be used in the SFP PWR tests : Report prepared in the framework of the OECD/NEA SFP Project

Steinbrück, M.; Jung, M.; Walter, M.

The thermo-hydraulic and ignition behavior of full-scale Pressurized Water Reactor (PWR) fuel assembly mock-ups during hypothetic spent fuel pool Loss of Coolant Accidents (LOCA) will be investigated in the frame of the OECD-NEA Sandia Fuel Program (SFP).
The choice of the cladding alloy has been intensively discussed in the initial phase of the project. The PWR cladding alloys Zircaloy-4 or ZIRLO have been originally foreseen to be used in these tests. Due to problems regarding availability and proprietary rights of these materials, finally the Boiling Water Reactor (BWR) material Zircaloy-2 was selected as heater rod material. The main arguments for Zry-2 were availability of material and all data, the positive experience with the material during the BWR test series and the very similar properties of Zry-2 and Zry-4. Some participants asked for a proof of the latter statement, especially because the database on Zry-2 is scarce in comparison with Zry-4. In this context KIT performed a series of separate-effects tests (SETs) to confirm the similarity of the two alloys and to deliver corresponding data. The following report present ... mehr

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DOI: 10.5445/IR/1000051640
Seitenaufrufe: 28
seit 01.06.2018
Downloads: 46
seit 14.01.2016
Zugehörige Institution(en) am KIT Institut für Materialforschung (IMF)
Publikationstyp Forschungsbericht
Jahr 2010
Sprache Englisch
Identifikator urn:nbn:de:swb:90-516408
KITopen-ID: 1000051640
Verlag KIT, Karlsruhe
Umfang IV, 38 S.
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