Separation of nuclear material in alkali chloride baths by precipitation technique

Ibe, Junya*; Takahatake, Yoko  ; Watanabe, So  ; Watanabe, Masayuki; Asanuma, Noriko*; Matsuura, Haruaki*

Since waste salt generated from pyro-reprocessing test which contains uranium can easily capture moisture from the air and corrode equipment and piping material, further treatment technology for decontamination and waste stabilization is required. The aim of this study is to develop a simple separation method for decontamination of salts. First, LiCl-KCl eutectic and NaCl-2CsCl salts were used as melt baths, lithium oxide was used as a precipitant, and cerium chloride was used as uranium surrogate for testing the precipitation process in glove box. Next, since the actual waste salt is precipitated outside the glovebox. From the results obtained by structural analysis and XRD on precipitates generated, it is considered that oxychloride was formed by the similarity in EXAFS oscillation and X-ray diffraction patterns.