Methodology of the source term estimation for DEMO reactor

tThe problem of source term qualification is one of the most important topics in order to predict possiblereleases of the Activation Products (APs) and Tritium from the DEMO Fusion reactor. The preventionof any possible consequence, which can affect the environment and the population, is the mission ofFusion technology. In the frame of the EUROfusion Work Package of Safety and Environment (WPSAE)a methodology to scale and evaluate the source terms assessed for ITER and the Fusion Power PlantConceptual Study (PPCS) has been studied.This paper refers to the activity currently conducted for the DEMO source terms assessment and thepreliminary results obtained. During activities in the task, the methodology was developed for the evalua-tion of Tritium and APs concentration inventory. The methodology is explained in detail for the predictionof the Tritium and APs concentration in Vacuum Vessel (VV) and in the Breeding Blanket (BB) startingfrom the DEMO current design data and the inventories assumed in ITER, PPCS and SEAFP programs. Theseresults refer to the Helium Cooled Lead Liquid (HCLL) and the Helium Cooled Pebble Bed (HCPB) concepts.The approach is based on the foundations, set in the fission technology safety analysis of the Design BasisAccidents (DBA), Design Extension Conditions (DEC) and Beyond Design Basis Accident (BDBA).