The Breeding Blanket (BB) is one of the key components European Demonstration (EU-DEMO) fusion reactor. Its main subsystems, Breeder Zone (BZ) and First Wall (FW), are cooled by two independent cooling circuits, called Primary Heat Transfer Systems (PHTS). Evaluating BB PHTS performances in anticipated transient accident conditions a relevant issue for design these systems. Within framework EUR...

The presented article discusses developing and validation of a VVER 1000 TRACE V5.0p5 model. Developing such model for computer code is important as it increases the capability analyses in simulating nuclear power plant behaviour different accidents including capabilities 3D thermal hydraulic phenomena reactor core simultaneously with physics calculations. In this way, possible to conduct trans...

Code assessment and validation is one of the most relevant research lines in thermal hydraulics best estimate codes. During last decades, Nuclear Energy Agency (NEA) Organization for Economic Co-operation Development (OECD) have sponsored dozens experimental projects this field. Most them were compiled CSNI Validation Matrix 1996. Several been promoted new century as SETH, PKL, PKL-2, PKL-3 PKL...

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...