Overview of the Experimental Helium Cooling (EHCL) system

Abstract

The objective of the Experimental Helium Cooling (EHCL) facility at IPR is to contribute to the development of the helium cooled nuclear fusion components such as tritium breeding blanket and divertor by providing experimental data on the mock-up testing of these components. All these mock-ups have several complex cooling circuits created for efficient heat extraction by high pressure helium gas. Several such mock-ups to be tested beforehand for evaluating the thermal performance and concluding the design & fabrication techniques of tritium breeding blankets and divertors. Moreover, studying performance of the integrated plant, learning behaviour of different EHCL components e.g. circulators, heat exchangers, heaters, compressors & valves etc., and demonstration of operational & control scheme under different operating conditions are essential for development of the helium cooling system (HCS) for Indian Test Blanket Module (TBM) for ITER. This paper describes the EHCL facility that is being commissioned at IPR. It briefly presents results of the thermo-hydraulic studies of the integrated system. It also talks about its major components and their performance results, operation and control scheme of the loop, and highlights the key features of the data acquisition & control system of the facility.