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The zirconium based alloys are widely used as cladding materials for nuclear fuels in commercial reactors. The fuel cladding creep test data including temperature and/or load drops is valuable for building the understanding of recovery phenomena in zirconium alloys during creep, but also scarce in open literature. The actions related to the preparation for the transient creep tests for Zirconium-based fuel cladding materials are briefly described in this report.
|Publisher||VTT Technical Research Centre of Finland|
|Publication status||Published - 2017|
|MoE publication type||D4 Published development or research report or study|
|Series||VTT Research Report|
- cladding creep
- experimental research