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Journal Articles

Development of advanced reprocessing system based on precipitation method using pyrrolidone derivatives as precipitants; Overall evaluation of system

Ikeda, Yasuhisa*; Kawasaki, Takeshi*; Harada, Masayuki*; Nogami, Masanobu*; Kawata, Yoshihisa*; Kim, S.-Y.*; Morita, Yasuji; Chikazawa, Takahiro*; Someya, Hiroshi*; Kikuchi, Toshiaki*

Proceedings of International Conference on Toward and Over the Fukushima Daiichi Accident (GLOBAL 2011) (CD-ROM), 5 Pages, 2011/12

An advanced reprocessing system for spent FBR fuels based on two precipitation processes using pyrrolidone derivatives as precipitants has been developed. Experimental results of precipitation behavior of U, Pu and other elements, the heat- and radiation-resistance of precipitants, the thermal decomposition properties of precipitates showed that N-n-butyl-2-pyrrolidone and N-neopentyl-2-pyrrolidone are the appropriate precipitants for the first and second precipitation steps, respectively. From the engineering investigation, We confirmed that the precipitation and the filtration can be done efficiently using the engineering scale equipment and that the fuel pellets are directly prepared by the calcination of the precipitates. On the basis of these results, we evaluated that the proposed system is expected to be one of candidates of the future reprocessing systems for spent FBR fuels.

Oral presentation

Development of advanced reprocessing system using highly selective and controllable precipitants, 22; Applicability assessment of precipitation and fuel processing steps by the engineering scale experiment using uranium

Kikuchi, Toshiaki*; Chikazawa, Takahiro*; Someya, Hiroshi*; Morita, Yasuji; Ikeda, Yasuhisa*

no journal, , 

We have been developing an advanced reprocessing system for spent FBR fuels based on precipitation method using pyrrolidone derivatives. Precipitation behavior of U(VI), separation and washing of the precipitate and the operability of engineering scale equipment were examined using solutions of U(VI) and simulated fission products. The precipitate obtained was used in basic and engineering scale tests for precipitant recovery step and fuel production step. The results showed the feasibility of the system from an engineering point of view.

Oral presentation

Technology succession through assembling the dummy fuel assembly at the Irradiation Rig Assembling Facility (IRAF)

Itagaki, Wataru; Noguchi, Koichi; Endo, Norio; Nakamura, Toshiyuki; Ashida, Takashi; Saito, Takakazu; Someya, Hiroyuki*; Tomine, Hiroshi*; Kato, Jun*; Gunji, Masakatsu*

no journal, , 

no abstracts in English

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