The EU-DEMO Water-Cooled Lithium-Lead (WCLL) Breeding Blanket (BB) main subsystems to be cooled are the Breeder Zone (BZ) and First Wall (FW). Each subsystem will equipped with an independent Primary Heat Transfer System (PHTS). Within framework of EUROfusion Work Package research program, several accidents belonging category “Decrease in Coolant Flow Rate” were studied. activity was aimed at e...

In the framework of a Coordinate Research Project (CRP) endorsed by International Atomic Energy Agency (IAEA), Department Astronautical, Electrical and Engineering (DIAEE) Sapienza University Rome has developed thermal–hydraulic model Fast Flux Test Facility (FFTF). FFTF was Sodium-cooled Reactor (SFR) Westinghouse Electric Corporation for U.S. Energy, which operated from 1980 to 1992. The main...

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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 (W...

Thermal hydraulic system codes are complex tools developed to estimate the transient behaviour of nuclear power plants (NPPs) during off-normal conditions. The evaluation of safety margins, the operator training, the optimization of the plant design and related emergency procedures are some of the major applications of these codes. Best estimate computer codes are used to calculate postulated a...