Development of FR fuel cycle in Japan, 2; Basic design and verification of U-Pu-Np co-recovery flowsheets for engineering scale hot examinations in Japan

Nakabayashi, Hiroki ; Nagai, Toshihisa 

We performed a basic design of the solvent extraction test system with centrifugal contactors for the engineering-scale hot examination facility to ensure the development and commercialization of the advanced aqueous reprocessing technology for fast reactor fuels in Japan. The system was designed to have the ability to operate two different flowsheet, the simplified solvent extraction method and the co-processing method, which we proposed as promising solvent extraction processes. In the design, various engineering issues, such as error of flow rate of reagent pumps and a dissolver solution feeder, error of chemical analyses and environmental temperature fluctuation, were delt with. For the design we modified and used the computer code "MIXSET-X" which was developed to simulate solvent extraction system by JAEA in 1999. The validity of the modified code was benchmarked by comparison with an engineering scale uranium test.