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Ibe, Junya*; Aso, Megumi*; Watanabe, Masayuki; Watanabe, So; Takahatake, Yoko; Matsuura, Haruaki*
no journal, ,
no abstracts in English
Ibe, Junya*; Aso, Megumi*; Takahatake, Yoko; Watanabe, So; Watanabe, Masayuki; Matsuura, Haruaki*
no journal, ,
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. In the first step, oxides are added as oxygen donor in the melts to uranium. In the next step, melt bath components are evaporated by a vacuum distillation. 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. By characterization with XRD and EXAFS, it is considered that oxychloride was formed. By pulverization of the salt and increase the distillation time, distillation ratio of the salt from the sample was achieved up to 90%.
Ibe, Junya*; Takahatake, Yoko; Watanabe, So; Watanabe, Masayuki; Asanuma, Noriko*; Matsuura, Haruaki*
no journal, ,
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.
Ibe, Junya*; Mitani, Mao*; Takahatake, Yoko; Watanabe, So; Watanabe, Masayuki; Matsuura, Haruaki*
no journal, ,
no abstracts in English
Ibe, Junya*; Mitani, Mao*; Takahatake, Yoko; Watanabe, So; Watanabe, Masayuki; Matsuura, Haruaki*
no journal, ,
no abstracts in English
Ibe, Junya*; Aso, Megumi*; Takahatake, Yoko; Watanabe, So; Watanabe, Masayuki; Matsuura, Haruaki*
no journal, ,
no abstracts in English
Ibe, Junya*; Mitani, Mao*; Takahatake, Yoko; Watanabe, So; Watanabe, Masayuki; Asanuma, Noriko*; Matsuura, Haruaki*
no journal, ,
Ibe, Junya*; Aso, Megumi*; Takahatake, Yoko; Watanabe, So; Watanabe, Masayuki; Matsuura, Haruaki*
no journal, ,
Since waste salt generated from pyro-reprocessing test which contains uranium can easily capture moisture and corrode equipment, further treatment technology for decontamination. Oxides are added as oxygen donor in the melts, and then uranium is separated from the salt as precipitates. In the next step, melt bath components are evaporated by a vacuum distillation. 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. Next, a distillation line has been constructed and the best condition for distillation has been searched. Amount of the precipitates increased with increasing the amount of oxide, and recovery ratio of cerium must potentially depend on solubility of oxychloride into the bath salts. It is considered that oxychloride was formed by the similarity in EXAFS oscillation and X-ray diffraction patterns.
Ibe, Junya*; Takahatake, Yoko; Watanabe, So; Watanabe, Masayuki; Matsuura, Haruaki*
no journal, ,
no abstracts in English
Yamamoto, Yuri*; Mitani, Mao*; Ibe, Junya*; Takahatake, Yoko; Watanabe, So; Watanabe, Masayuki; Matsuura, Haruaki*
no journal, ,
Various waste salts are generated in the development of the pyroprocessing method. In the previous study, cerium was used as a nuclear fuel simulant, and they succeeded in precipitation experiments using lithium oxide and evaporation of bath salts. We have tried to search for more optimal precipitation conditions by using lithium carbonate as a precipitant and introducing air without using a precipitant. In addition, using manganese, which has a higher valence than uranium, as a simulant, we have tried to reproduce the precipitate. In the experiment using lithium carbonate precipitant, higher precipitation rate was obtained, and precipitation using oxygen in the air was also successful. In an experiment using manganese, oxide precipitate was also successfully produced. It was found that both cerium and manganese reacted with the precipitant in the molten salt.