Thermal Hydraulic Analysis and Design of ITER Secondary Cooling Loop CCWS-2F

The thesis focuses on the preliminary design of the new Component Cooling Water System: CCWS-2F. The CCWS-2F will be installed alongside the current cooling water systems already in place to cool the Tokamak and key parts of ITER, the International Thermonuclear Experimental Reactor, which is presently being built in Cadarache, France. In order to meet the requirements of the ITER new Baseline, which was established in 2024, CCWS-2F was designed to meet the additional cooling requirements, mainly for the Electron Cyclotron Heating (ECH) and Diagnostic systems. Important changes to this baseline approach, like switching the Blanket First Wall's beryllium to tungsten, necessitate a major improvement in the ECH system, raising its heating capacity from 20 MW to 67 MW. For ECH and diagnostic systems to function reliably throughout several operational phases, including the Start of Research Operation (SRO) Phase and the Deuterium-Tritium Phases (DT-1, DT-2), new cooling requirements must be satisfied. Maintaining stringent operating parameters like pressure, temperature, flowrate, and water quality is CCWS-2F's main goal. The process design of the hydraulic circuit is given special attention in this thesis. CCWS-2F will be thoroughly modeled and sized using AFT Fathom, a fluid dynamic program selected for its ability to compute pipe flow distribution for intricate CCWS-2F design activities, included the preparation of main process engineering documentations, such as Piping and Instrumentation Diagram (P&ID), Process Flow Diagram (PFD), and 3D modelling using AVEVA E3D.