Evaluation of the thermal-hydraulic performances of a once-through steam generator in nuclear fusion applications

Abstract After decades of operation in nuclear power plants, Once-Through Steam Generators (OTSGs) were recently proposed for fusion applications. In particular, they are supposed to be installed the primary cooling systems European Union Demonstration plant (EU-DEMO). One key reactor components is Breeding blanket (BB). Among BB concepts that currently under study, Water-Cooled Lithium-Lead (WCLL) option was considered this work. The WCLL divided two main subsystems, breeder zone (BZ) and first wall (FW), each one provided with an independent circuit, named Primary Heat Transfer System (PHTS). Thermal removed from by BZ FW PHTS driven Power Conversion (PCS) converted into electricity. thermal coupling ensured OTSGs per system. At Department Astronautical, Electrical Energy Engineering (DIAEE) Sapienza University Rome, a simulation activity carried out understand component thermal-hydraulic behavior during DEMO normal operations. For calculation purposes, full model steam generator prepared using modified version RELAP5/MOD3.3 system code. computational performed allows preliminary characterize OTSG performances both pulse dwell phases.