Post-Test Numerical Analysis of a Helium-Cooled Breeding Blanket First Wall under LOFA Conditions with the MELCOR Fusion Code

The validation of numerical tools employed in the analysis incidental transients a fusion reactor is topic main concern. KIT taking part this task providing both experimental data and by performing support codes used for safety analyses Helium Cooled Pebble Bed (HCPB) blanket concept. In recent years, an campaign has been performed KIT-HELOKA facility to investigate behavior First Wall Mock-Up (FWMU) under Loss Of Flow Accident (LOFA) conditions. aim was twofold: check expected DEMO thermal-hydraulics conditions during normal off-normal provide robust code validation. present work these efforts, it deals with LOFA system MELCOR 1.8.6 fusion. A best-estimate methodology ease distinction between user’s assumptions limitations. are here described together their goals, achievements, lesson learnt.