Modeling tritium transport in fusion reactors: Recent improvements in fusion-adapted MELCOR

For over 20 years, MELCOR has been adapted at INL for fusion reactor systems Modifications to MELCOR 1.8.2 were designed to accommodate needs for analysis of the ITER reactor; V&Vd for ITER NSSR 1&2, GSSR, RPrS, still in use today Additional modifications to later versions of MELCOR (1.8.5/1.8.6) were made to model advanced fusion reactor concepts, including: RELAP/ATHENA fluid properties including Li, PbLi, FLiBe, real EOS for hydrogen, helium (recently significantly revised and expanded, to include Sn, SnLi) Lithium pool fire models similar to LITFIRE Aerosol resuspension models Different multiphase fluids in different loops These models were integrated with tritium transport code TMAP into a single code based on MELCOR 1.8.6, which we call MELCOR-TMAP