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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

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