The move to high burnup fuels, new fuel designs and introduction of new cladding materials have generated a need to re-examine and verify the validity of the safety criteria for LOCA accidents. Fuel designers and nuclear research community, as well as the safety authorities rely on fuel performance codes for predicting the behaviour and life-time of fuel rods. The simulation tools are developed and validated on the basis of experimental results. The present report demonstrates the team capacity to analyse LOCA conditions on the base of the Halden experiment IFA 650.2 by means of the TRANSURANUS code and results are compared with experimental data.