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Morita, Yasuji; Yamagishi, Isao; Tsubata, Yasuhiro; Matsumura, Kazumi; Sakurai, Koji*; Iijima, Takahiko
JAEA-Research 2012-031, 39 Pages, 2012/11
JAEA-Research-2012-031.pdf:4.87MBJAEA-Research-2012-031(errata).pdf:0.14MB
Solvent extraction process with di-2-ethylhexylphosphoric acid has been developed for the purpose of Mo separation from high-level radioactive liquid wastes (HLLW). Mo has very low solubility in borosilicate glasses and makes so-called yellow phase when it contained beyond the solubility. After extraction and back-extraction data of Mo and other fission products were obtained by batch extraction tests, continuous extraction tests with simulated HLLW were performed using mixer-settler twice. At the second test, reduction of Y extraction yield and increase of Mo and Zr back-extraction yield were obtained compared with the results of the first tests, but those values should be still improved. Process simulation technique was developed using simulation code named PARC-MA, and the optimized process condition was obtained by the simulation.
Morita, Yasuji; Yamagishi, Isao; Matsumura, Kazumi; Iijima, Takahiko; Matsumura, Tatsuro
no journal, ,
As a part of the development of high-level liquid waste (HLLW) conditioning technology for advanced nuclear fuel cycle, separation process for Mo by extraction with HDEHP (di-2-ethylhexylphosphoric acid) is being developed as the first separation step for HLW. Separation behavior of various elements in continuous counter-current extraction was examined by an experiment with simulated HLLW using mixer-settler units. The results showed possibility to establish the separation process for Mo by extraction with HDEHP.
Morita, Yasuji; Yamagishi, Isao; Iijima, Takahiko
no journal, ,
Development of high-level liquid waste (HLW) conditioning technology for advanced nuclear fuel cycle was conducted for the purpose of the reduction of potential problems in the verification process for HLW. It includes development of separation technology for Mo, Pd and Ru from HLW and development of separate treatment of the insoluble residue. The method of washing the insoluble residue before solidification of the residue was studied using real insoluble residue obtained by dissolution of spent nuclear fuel. Washing by nitric acid and oxalic acid was found to contribute to the reduction of contamination with Zr and 
-emitters. Metal alloy component in the insoluble residue, Mo, Tc, Ru, Rh and Pd did not change its composition even after the washing.
Morita, Yasuji; Yamagishi, Isao; Iijima, Takahiko; Sakurai, Koji
no journal, ,
As a part of the development of high-level liquid waste (HLLW) conditioning technology for advanced nuclear fuel cycle, separation process for Mo by extraction with HDEHP (di-2-ethylhexylphosphoric acid) is being developed as the first separation step for HLW. Separation behavior of various elements in continuous counter-current extraction was examined by an experiment with simulated HLLW using mixer-settler units. The results of the continuous extraction and process simulation calculations by PRAC-MA code showed enough possibility to establish the separation process for Mo by extraction with HDEHP.
Yamagishi, Isao; Sakurai, Koji; Iijima, Takahiko; Morita, Yasuji; Kirishima, Akira*
no journal, ,
no abstracts in English
Matsumura, Tatsuro; Iijima, Takahiko; Takano, Masahide
no journal, ,
no abstracts in English
Matsumura, Tatsuro; Iijima, Takahiko; Ishii, Sho; Takano, Masahide; Onozawa, Atsushi
no journal, ,
no abstracts in English