• Ansys
• Critical Heat Flux
• FEM
• Pipe stress analysis

The present work has been performed in framework of the research program between Gruppo di Ricerca Nucleare San Piero a Grado of the University of Pisa and Nuclear and Indusrtial Engineering srl. The research aimed at the design and construction of a test facility for the experimental investigation of Critical Heat Flux phenomena at the same conditions as the reference PWR. THe present thesis is related to the structural analysis of the test facility, having the purpose of otimizing the facility layout and designing the support structure in compliance with the applicable regulations. Reference was made ASME VIII-Boiler and Pressure Vessel Code, adopted both for pipilines and for vessels. The analysis were performed by means of Finite Element Method using ANSYS APDL MECHANICAL release 15.0 and ANSYS WORKBENCH release 15.0 codes.