Loading...
Loading...

Go to the content (press return)

Development of the new AINA code and its application to the Safety Analysis of the European DEMO designs

Author
Baeza, E.
Type of activity
Theses
Other related units
Department of Physics
Defense's date
2019-07-22
URL
http://hdl.handle.net/2117/166970 Open in new window
Abstract
A conclusion that can be drawn from the historical safety analyses developed for tokamaks fusion reactors is that some of the major risks involve incidents in the vacuum vessel. In order to evaluate plasma evolution and in-vessel components strains, a safety code called AINA was developed during the last ten years for different fusion reactors designs as ITER and the Japanese DEMO design WCPB. The present document includes an in-depth critical analysis of these former AINA versions, a new codifi...
Group of research
ANT - Advanced Nuclear Technologies Research Group
Citation
Baeza Pérez, E. Development of the new AINA code and its application to the Safety Analysis of the European DEMO designs. Tesi doctoral, UPC, Departament de Física, 2019.

Participants

Attachments