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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

 Times Cited Count:3 Percentile:24.17(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.

JAEA Reports

Investigation of low decontamination pellet fuel manufacture line composition

*; *; *; Tamaki, Yoshihisa*; *

JNC TJ9420 2003-003, 133 Pages, 2003/02

JNC-TJ9420-2003-003.pdf:4.79MB

As 2nd fiscal year of phase II of FBR cycle utilization strategy investigation research, following on the denitration conversion process 1ast year, the apparatus design in consideration of remote automation, line composition, and the arrangement design in a cell were performed, and the following result was obtained in this examination about each equipment from pelletizing process to former part of fuel element assembling process of a low decontamination pellet manufacture plant. (1)The outline structure design of each equipment based on remote automatic operation and the conceptual design of a process were performed, and technical formation nature was checked. (2)The formation nature of a maintenance system which conveys the units to maintenance area and repairs was checked at the time of a trouble. (3)The information about failure of the units of each equipment was examined, and operating ratio was evaluated using the plant characteristic simulator which took the throughput and buffer capacity for every process as parameters. (4)About the arrangement plan of equipments in a building, reexamination the arrangement plan of phase I by reflecting the design progress result of each equipment was performed, and accuracy was raised.

JAEA Reports

Foprmation nature investigation of a denitration conversion equipment concept

*; *; *; Tamaki, Yoshihisa*; *

JNC TJ9420 2003-002, 25 Pages, 2003/02

JNC-TJ9420-2003-002.pdf:4.07MB

In this examination, based on the turntable type denitration conversion equipment concept designed last fiscal year, the denitration contaniner made from ceramics was manufactured, the quality tests of powder obtained by microwave denitration of nitric acid uranium solution, calcination, and reduction were performed. The soundness of a denitration container was also checked, and the following result was obtained. (1)As the result of microwave denitration of nitric acid uranium solution in the manufactured denitration container, the usual foamind object was obtained. (2)Denitration product was roughly milled by auger and the prospet to obtain uniform powder was acquired. (3)Physical properties of the powder after calcination and reduction were measured, and the powder was almost equivalent to the conventional one obtained by microwave denitration. (4)Based on the examination result, the formation nature of turntable type denitration conversion equipment was discussed and the development subject was arranged.

JAEA Reports

Ther study of characteristic evaluation techniques about nuclear fuel pellet manufacturing system (2)

*; *; *; Tamaki, Yoshihisa*; *

JNC TJ9400 2003-010, 66 Pages, 2003/02

JNC-TJ9400-2003-010.pdf:4.03MB

In this study, while examining the operating ratio which took into consideration the operation characteristics of apparatus for the low decontamination pelltizing method, and apparatus exchange frequency as the 2nd fiscal year of phase II of FBR cycle utilization strategy investigation research, the system characteristics evaluation simmulator was modified to able to calculate waste amount generated by fixed exchange of the parts. A comparison study of the operating ratio in a few other fabrication system was also performed by applying the simulator to them, and the following result was obtained. (1)While arranging the setting plan of operation characteristics of apparatus in connection with the apparatus operating ratio, optimization of the buffer capacity, throughput, and the number which improve operating ratio was performed. (2)The calculation program of waste amount generated which can respond to the case of fixed exchange of the parts, and the case parts of exchange at the time of failure was made. (3)The comparison method of the system characteristics among fabrication systems was considered, and comparison examination of operating ratio was performed by applying to the other fuel fabrication systems. (4)The simpler method for data input of the characteristic evaluation simulator manufactured in the last fiscal year was examined, and the simulator modification was carried out.

JAEA Reports

Study of assessing aqueous reprocessing process for the pipeless reprocessing plant -II

*; *; *; Fumoto, Hiromichi*; *; *

JNC TJ9400 2001-005, 128 Pages, 2001/03

JNC-TJ9400-2001-005.pdf:3.81MB

The purpose of this study is to investigate the possibility of adopting new reprocessing process by introducing pipeless plant concept, combined with aqueous separation methods other than solvent extraction method to be adopted to develop more economical FBR fuel (MOX fuel) reprocessing process. In this year, the following studies were made with technical view of interest for the purpose of evaluating the feasibility of the pipeless reprocessing plant adopting crystallization method and peroxide precipitation method, which are featured to be suitable to batch process, through the investigation in last year. (1)Process flow optimization for crystallization method and peroxide precipitation method (2)Material balance analysis and major equipment designing (3)Conceptual study on the pipeless plant adopting crystallization method and peroxide precipitation method (4)Construction cost evaluation of the pipeless plant adopting crystallization method and peroxide precipitation method (5)Extracting task to be solved and their possible way of solutions

JAEA Reports

Pu(IV) Nitrate crystallization behavior confirmation experiment

*; *; *; *

JNC TJ8400 2000-061, 92 Pages, 2000/03

JNC-TJ8400-2000-061.pdf:8.79MB

Crystallization procedure is considered to have an advantage in recovering rather pure uranium from contaminated uranium solution and to be applicable for a new reprocessing process. It was confirmed until last year that the reprocessing process with crystallization procedure has a sufficient advantage. But the data for Pu crystallization is very rare. although it is necessary for design of the process with crystallization procedure. In this study, a beaker scale plutonium test was performed in AEA Technology Harwell Laboratory to confirm a behavior of Pu (IV) nitrate under crystallization condition. The results were examined by Mitsubishi Materials Corporation. Test item was a measurement of temperature in case of Pu (IV) nitrate crystallization or freezing of the solution in the following six parameters. (Pu(g/L):200, 100, 50, HNO$$_{3}$$(m):6, Pu valence:4). (Pu(g/L):200, 100, 50, HNO$$_{3}$$(m):4, Pu valence:4). Test results were as follows. (1)Pu(IV) nitrate crystallization was not observed even in the case 200g Pu/L and HNO$$_{3}$$ 6M and 4M which were considered to the best condition but crystal of H$$_{2}$$O and HNO$$_{3}$$ $$cdot$$ 3H$$_{2}$$O were observed. (2)Similar results were obtained for the other parameter with lower Pu concentration. (3)We can estimate that Pu(IV) nitrate crystallization will not occurred in the reprocessing process with crystallization procedure. (4)The solubility data of Pu(NO$$_{3}$$)$$_{4}$$ - HNO$$_{3}$$-H$$_{2}$$O system was obtained.

JAEA Reports

Study of assessing aqueous reprocessing process for the pipeless reprocessing plant

*; *; Fumoto, Hiromichi*; *; *

JNC TJ9400 2000-001, 112 Pages, 2000/02

JNC-TJ9400-2000-001.pdf:6.67MB

The purpose of this study is to investigate the possibility of new reprocessing process for the purpose of introducing pipeless plant concept, where aqueous separation methods other than solvent extraction method are adopted in order to develop more economical FBR fuel (MOX fuel) reprocessing process. At it's first stage, literature survey on precipitation method, crystallization method and ion-exchange method was performed. Based on the results, following processes were candidated for pipeless reprocessing plant. (1)The process adopting crystallization method and peroxide precipitation method (2)The process adopting oxalate precipitation method (3)The process under mild aqueous conditions (crystallization method and precipitation method) (4)The process adopting crystallization method and ion-exchange method (5)The process adopting crystallization method and solvent extraction method The processes (1)$$sim$$(5) were compared with each others in terms of competitiveness to the conventional reference process, and merits and demerits were evaluated from the viewpoint of applicability to pipeless reprocessing plant, safety, economy, Efficiencies in consumption of Resources, non-proliferation, and, Operation and Maintenance. As a result, (1)The process adopting crystallization method and peroxide precipitation method was selected as the most reasonable process to pipeless plant. Preliminary criticality safety analyses, main process chemical flowsheet, main equipment list and layout of mobile vessels and stations were reported for the (1) process.

Oral presentation

Development of a simple reprocessing process by selective precipitation for uranyl ions

Kikuchi, Toshiaki*; Yamasaki, Kazuhiko*; Kusama, Makoto*; Chikazawa, Takahiro*; Tamaki, Yoshihisa*; Hanzawa, Masatoshi*; Koshino, Nobuyoshi*; Asanuma, Noriko*; Harada, Masayuki*; Kawata, Yoshihisa*; et al.

no journal, , 

no abstracts in English

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