Nuclear Fuel Behaviour in Loss-of-coolant Accident (LOCA) Conditions: State-of-the-art Report

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The present report has been prepared by the Committee on the Safety of Nuclear Installations (CSNI) Working Group on Fuel Safety (WGFS) and covers the following technical aspects:

  • description of different LOCA scenarios for major types of reactors: BWRs, PWRs, VVERs and to a lesser extent CANDUs;
  • LOCA phenomena: ballooning, burst, oxidation, fuel relocation and possible fracture at quench;
  • details of high-temperature oxidation behaviour of various cladding materials;
  • metallurgical phase change, effect of hydrogen and oxygen on residual cladding ductility;
  • methods for LOCA testing, for example two-sided oxidation and ring compression for ductility, and integral quench test for strength;
  • predictive computer codes.