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Kai, Masao; Iwamoto, Toshihiro; Saito, Madoka*; Takahatake, Yoko; Watanabe, So; Nakamura, Masahiro; Tsukahara, Takehiko*; Itoda, Naokazu*; Naruse, Atsuki*
no journal, ,
The sludges containing uranium are generated in nuclear fuel fabrication process and have been stored in nuclear fuel fabrication facilities. Uranium is suggested to be selectively recovered from the solution in which the sludges are immersed. In this study, the oxide conversion tests were carried out with the gel obtained by the temperature swing extraction tests with cerium. The most effective heating temperature for the oxide conversion of was determined as 1000 degree Celsius. Based on the results of tests with cerium, the oxide conversion tests with uranium gel were also carried out. The gel was heated at 1000, and products were specified according to analysis data.
Kai, Masao; Sato, Takanori*; Iwamoto, Toshihiro; Saito, Madoka*; Nakahara, Masaumi; Takahatake, Yoko; Watanabe, So; Nakamura, Masahiro; Naruse, Atsuki*; Itoda, Naokazu*; et al.
no journal, ,
The sludges containing uranium are generated in the nuclear fuel fabrication facilities. Uranium is planned to be selectively recovered from the sludge leachate. The temperature swing extraction method was selected for the selective recovery of uranium. In this study, a small-scale testing system was developed, and the performances of the agitation, the transportation of the gel-containing solution, and the separation of the gel were experimentally examined. Cerium(IV) was used instead of uranium, and agitator blades were selected to agitate the gel solution effectively. The gel solution was transferred through the self-feeding pump and was successfully separated into the gel and the solution using the spin dryer with a filter cloth.