Studies of materials for molten salt nuclear applications

This paper presents a set of experiments aimed at an evaluation of the behaviour of different materials in contact with liquid or solid media likely to be encountered in a molten salt nuclear reactor. Operation of a molten fluoride loop made of graphite is described. Tests are undertaken for the study of steel corrosion by fluorides or liquid lead and molten fluorides. Metal and carbon transfers in a mixture of molten fluorides are evidenced. Tests show that steel is wetted preferentially by lead and not by molten fluorides thus avoiding salt deposition in the heat exchanger