The experimental database currently being reviewed includes the following programmes:
• AECL experiments conducted on fission product release in air; results are relevant to CANDU loss of end-fitting accidents;
• VERCORS tests on FP release and transport conducted by CEA in collaboration with IRSN and EDF; additional tests may potentially be conducted in more oxidizing conditions in the VERDON facility;
• RUSET tests by AEKI investigating ruthenium transport with and without other FP simulants;
• Experiments by VTT on ruthenium transport and speciation in highly oxidizing conditions.
In addition to the above, at IRSN and at ENEA modelling of fission product release and of fuel oxidation is being pursued, the latter being an essential boundary condition influencing ruthenium release.
Reactor scenario studies have been carried out at INR, EDF and IRSN: calculations of air ingress scenarios with respectively ICARE/CATHARE V2; SATURNE-MAAP; and ASTEC codes provided first insights of thermal-hydraulic conditions that the fuel may experience after lower head vessel failure.
This paper summarizes the status of this work and plans for the future.