Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Kudo, Atsunari; Kurabayashi, Kazuaki; Yanagibashi, Futoshi; Sasaki, Shunichi; Sato, Takehiko; Fujimoto, Ikuo; Obu, Tomoyuki
Proceedings of 2017 International Congress on Advances in Nuclear Power Plants (ICAPP 2017) (CD-ROM), 6 Pages, 2017/04
The Co-processing process is the extraction process to recover Pu/U mixed product solution with given Pu/U ratio for improving of nuclear proliferation resistance. In addition, Np is also recovered with U and Pu because Np is one of minor actinides and a long-lived radionuclide and Np has the extractability into TBP solvent. Development of its flowsheet achieves to decrease environmental effect of waste materials. The orientation of development about Co-processing process is to demonstrate of reprocessing the future spent fuels from a LWR, a LWR-MOX hybrid, and a FR-MOX with one cycle. We demonstrated by use of miniature reflux-type centrifugal contactors at the partitioning unit. The test conditions of the Pu/U ratio in the loaded solvents were 1%, 3%, and 5% considering the composition of spent fuels. We used the HAN as the reductant of Np (VI) for back extraction. The results of these tests were very good. We got the prospect of U, Pu, and Np Co-processing flowsheet.
Kudo, Atsunari; Yanagibashi, Futoshi; Hoshi, Takahiro; Tada, Kazuhito; Sato, Takehiko; Fujimoto, Ikuo; Obu, Tomoyuki
no journal, ,
no abstracts in English
Kudo, Atsunari; Yanagibashi, Futoshi; Tada, Kazuhito; Hoshi, Takahiro; Fujimoto, Ikuo; Obu, Tomoyuki
no journal, ,
no abstracts in English
Kurabayashi, Kazuaki; Kudo, Atsunari; Sato, Takehiko; Tada, Kazuhito*; Obu, Tomoyuki
no journal, ,
We are developing Np recovery with U and Pu in co-processing process (U and Pu co-recovery) because Np is one of minor actinides and a long-lived radionuclide. It is reported the flow sheet of U, Pu and Np co-recovery we set by MIXSET-X.
Kudo, Atsunari; Kurabayashi, Kazuaki; Yanagibashi, Futoshi; Sato, Takehiko; Fujimoto, Ikuo; Obu, Tomoyuki
no journal, ,
no abstracts in English
Kudo, Atsunari; Nagaoka, Shinichi; Kurabayashi, Kazuaki; Yanagibashi, Futoshi; Obu, Tomoyuki
no journal, ,
no abstracts in English
Takeuchi, Masayuki
no journal, ,
no abstracts in English
Sakamoto, Atsushi; Sano, Yuichi; Takeuchi, Masayuki
no journal, ,
no abstracts in English
Ono, Shimpei; Ichige, Yoshiaki; Shibata, Atsuhiro; Sato, Takehiko; Takeuchi, Masayuki
no journal, ,
no abstracts in English
Sakamoto, Atsushi; Sato, Takehiko; Sano, Yuichi; Takeuchi, Masayuki
no journal, ,
The PUREX process has been widely used in industrial reprocessing plants for spent nuclear fuel. It can separate uranium and plutonium individually from dissolved solution of spent nuclear fuel by solvent extraction technique. So, a risk of nuclear proliferation has to be considered as one of the subjects, the Japan Atomic Energy Agency (JAEA) has been developing a new extraction process, named as Co-processing process to decrease it. It can control to accompany plutonium with uranium in over-all solvent extraction stage using TBP (Tri-Butyl-Phosphate) as an extractant as well as the PUREX process. In this study, prior to the extraction test using genuine solution, uranium extraction behaviour on the Co-processing flowsheet and its robustness on flowrate increment were discussed using a centrifugal contactors system. Also, the decontamination effect on various flowsheet design was evaluated using rhenium (substitute for technetium) and zirconium.