Design of the Test Section for the Experimental Validation of Antipermeation and Corrosion Barriers for WCLL BB

Tritium permeation into the Primary Heat Transfer System (PHTS) of DEMO and ITER reactors is one challenging issues to be solved in order demonstrate feasibility nuclear fusion power plants construction. Several technologies were investigated as antipermeation corrosion barriers reduce tritium flux from breeder PHTS. Within this frame, alumina coating manufactured by Pulsed Laser Deposition (PLD) Atomic Layer (ALD) are two main candidates for Water Cooled Lithium Lead (WCLL) Breeder Blanket (BB). In validate performance coatings on relevant WCLL BB geometries, a mock-up was designed will characterized an experimental facility operating with flowing lithium-lead, called TRIEX-II. The present work aims illustrate preliminary engineering design deeply investigate hydrogen isotopes through PHTS water pipes. tests planned temperature range between 330 500 °C, deuterium partial pressure 1–1000 Pa. transport analysis carried out integration TRIEX-II also shown.