Report on an experimental campaign on cladding transient behaviour

Rami Pohja, Santtu Huotilainen

Research output: Book/ReportReport

Abstract

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.
Original languageEnglish
PublisherVTT Technical Research Centre of Finland
Publication statusPublished - 2017
MoE publication typeD4 Published development or research report or study

Publication series

SeriesVTT Research Report
VolumeVTT-R-00799-17

Keywords

  • cladding creep
  • experimental research

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