• DEMO
• ITER
• LOFA
• RELAP5
• TBS
• WCLL

ITER as the largest and most advanced fusion experiment in the world required an interface machine to connect in a commercial fusion power plant, DEMONstration fusion power plant. The DEMO design requires the design of a blanket system, which is suitable and reliable for Tritium (T) production and heat extraction for electricity production, the Test Blanket System (TBS). The Water-Cooled Lithium Lead (WCLL) is one of two candidates of TBS’s concepts, procured by EU.
This master thesis is devoted to develop a system thermal-hydraulic model using RELAP5 code of the WCLL TBM set and its ancillary systems of ITER to support the pre-conceptual design phase through the modelling, the simulations, and the analyses of selected operative conditions, NOS and LOFA.
A TH analysis was carried out by reviewing relevant documents of WCLL TBM, WCS, and Pb-Li Loop, collecting main geometrical data of systems, and constructing thermal-hydraulic model in RELAP5 code.