• static
• reactor
• piping
• nuclear
• ITER
• fusion
• dynamic
• CAESAR II
• ASME III
• ASME B31.3
• analysis
• stress

This Master Thesis applies ASME B31.3 standard to the piping analysis of the ITER nuclear fusion reactor.
The first part of this work is mainly focused on the main aspects related to the design and stress analysis of piping systems. Particular attention has been paid to the code criteria analyzing technical literature.
A comparison between the ASME B31.3 and the ASME Section III has been investigated in order to fully understand the different approaches for the design and validation of piping systems involved in different fields of application.
The last part of the thesis is focused on the application of the Piping software CAESAR II, developed by COADE, on the cooling lines systems of ITER nuclear fusion reactor. The analysis started with the 3d model reconstruction of pipelines and relative components. Subsequently static and dynamic loads were applied to the model in order to simulate the piping stresses under a wide range of normal and accidental conditions, such as seismic events and loss of vertical plasma control.
Several simulations have been performed in order to find the best configuration of the piping systems form the stress level point of view.