Hydrogen isotope permeation behavior in a blanket module using a novel gas-driven permeation device

Abstract The tritium permeation barrier (TPB) on reduced activation ferritic/martensitic steel is critical for ensuring both tritium self-sustainability and safety in fusion reactors. Evaluating the performance of TPB-containing modules with complex geometries is essential for advancing their engineering applications. In this study, a novel module-scale gas-driven permeation device was designed and established. The device, equipped with a custom-designed shielding shell, is capable of accommodating module samples several hundred millimeters in length. Utilizing this device, permeation fluxes of deuterium through module samples were recorded. The results demonstrated a significant PRF of FeCrAl/CLF-1 module due to a thermally grown oxide layer. However, the planar reference sample exhibited substantially higher PRF values, which might be due to the uniformity and density of the oxide layer. These findings highlight the importance of conducting module evaluations to ensure the reliable assessment of TPB performance in fusion reactor applications.