[en] The pyrochemical purification of plutonium has generated spent salts, which are disposed in nuclear facility. To reduce stored quantities, the development of a pyrochemical treatment is in progress. The feed salt, typically composed of various Pu and Am species spread into monovalent or divalent chloride matrix, is first oxidized to convert the actinides into oxides. Then the chlorides are separated from the actinide oxides by vacuum distillation. Temperatures higher than 750 deg C for mono-chloride salts mixture NaCl/KCl and higher than 1100 deg C for divalent CaCl₂ base salts, are required to produce an industrial flow of vaporization. Inactive qualification of the process for NaCl/KCl base salt has been carried with lanthanide surrogates. Then, a pilot equipment, called Distillator has been designed and built for production-scale distillation of NaCl/KCl and CaCl₂ oxidized plutonium salts. Industrial flows of vaporization have been obtained with this pilot equipment: about 4 g/cm²/h for NaCl/KCl at 800 - 900 deg C and 1 Pa, and more than 1.5 g/cm²/h for CaCl₂ base salts between 1000 - 1200 deg C at 0.1 Pa. The last step will be the integration of the Distillator into a glove box. (authors)