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Journal Articles

Development of a simple reprocessing process using selective precipitant for uranyl ions; Fundamental studies for evaluating the precipitant performance

Koshino, Nobuyoshi*; Harada, Masayuki*; Morita, Yasuji; Kikuchi, Toshiaki*; Ikeda, Yasuhisa*

Progress in Nuclear Energy, 47(1-4), p.406 - 413, 2005/00

https://doi.org/10.1016/j.pnucene.2005.05.040
 Times Cited Count：24 Percentile：81.01(Nuclear Science & Technology)

We have developed a simple reprocessing process for spent FBR fuels using N-cyclohexyl-2-pyrrolidone (NCP) which has selective precipitation ability for UO$$_{2}$$$$^{2+}$$ ions. It was confirmed that NCP has sufficient precipitation ability for UO$$_{2}$$$$^{2+}$$ ions, decontamination capability (separation of UO$$_{2}$$$$^{2+}$$ from simulated fission products), and resistance to $$gamma$$-ray radiation in nitric acid solutions. These findings indicate that NCP is applicable to our reprocessing process. We have also evaluated performances of other precipitants such as N-n-propyl-2-pyrrolidone (NProP), N-n-butyl-2-pyrrolidone (NBP), and N-n-butyl-2-pyridone (NBPyr). It was found that higher decontamination factors (DFs) are obtained by using NProP and NBP. This can be interpreted that the hydrophobicity of NProP and NBP is lower than that of NCP. Furthermore, we have obtained an experimental result that the resistance of NBPyr to $$gamma$$-ray radiation is superior to that of NCP.

Journal Articles

Development of a simple reprocessing process using selective precipitant for uranyl ions; Engineering studies on systems for precipitating and separating

Yamasaki, Kazuhiko*; Chikazawa, Takahiro*; Tamaki, Yoshihisa*; Kikuchi, Toshiaki*; Hanzawa, Masatoshi*; Morita, Yasuji; Ikeda, Yasuhisa*

Progress in Nuclear Energy, 47(1-4), p.414 - 419, 2005/00

https://doi.org/10.1016/j.pnucene.2005.05.041
 Times Cited Count：3 Percentile：23.28(Nuclear Science & Technology)

The simple reprocessing method based on precipitation using N-cyclohexyl-2-pyrrolidone (NCP) as a selective precipitant for U and Pu ions from dissolved solutions of spent FBR fuels has been developed. On the basis of fundamental studies on precipitation behaviors, we designed and built up the scaled-up laboratory equipments (1/20-scale of future plant capacity of 200 tHM/y) to evaluate technological and economical feasibility. This system, which mainly consists of a precipitator and a precipitate separator, should be operated continuously from economical reasons. From the experimental results, it was confirmed that the precipitator is capable of producing UO$$_{2}$$$$^{2+}$$-NCP precipitate stably with stipulated residence time (approximately 30 min), and the precipitate separator has the highly efficient separation of precipitate from the slurry. Furthermore, the parametric experiments indicated that the rinsing operation increased the efficiency in decontamination of FP elements.

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