Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Sasaki, Yuji; Tsubata, Yasuhiro; Shirasu, Noriko; Morita, Keisuke; Suzuki, Tomoya
Nihon Genshiryoku Gakkai Wabun Rombunshi, 14(3), p.202 - 212, 2015/09
We have been developing the new partitioning method of high-level radioactive waste by single-cycle extraction process. This process is composed of extraction of actinides (An) and fission products (FP, e.g., Pd, Ru, Mo and Tc), and mutual separation by back-extraction. The extractant employed in this process is required to extract soft, hard acid metals and oxonium anions simultaneously. The NTAamide (hexaoctyl-nitrilotriacetamide) is one of the candidate extractants. After extraction of An and FP, the mutual separation by back-extraction should be set up. Pd and Ru extracted by NTAamide can be back-extracted by complexing agents such as thiourea, systeine, diethylenetriamine, and trisaminoethylamine, and the back-extraction of Mo can be performed by methylimino-diethylacetamide (MIDEA), NTAamide(C2) and iminodimethylphosphoric acid, and Re can be done by aqueous phase with high pH.
Sasaki, Yuji; Tsubata, Yasuhiro; Shirasu, Noriko; Morita, Keisuke; Suzuki, Tomoya
Proceedings of 21st International Conference & Exhibition; Nuclear Fuel Cycle for a Low-Carbon Future (GLOBAL 2015) (USB Flash Drive), p.1653 - 1656, 2015/09
The concept for the new partitioning method of high-level radioactive waste (HLW) by single-cycle extraction process has been investigated. This process is based on extraction of actinides (An) and fission products (FP), and mutual separation by reverse extraction. Solo extractant and several stripping reagents will be utilized in this process. The extractant employed in this process is required to extract soft (platinum metals), hard acid metals(An), and oxonium anions (Mo, Tc) simultaneously. NTAamide is one of the candidate extractants. After extraction of An and FP by NTAamide(C8), the mutual separation among these metals by reverse extraction will be followed using the suitable water-miscible reagents. The extraction of An and FP, and the masking effect by some water-miscible reagents has been studied.
; ;
JNC TN8400 2001-022, 60 Pages, 2001/03
JNC-TN8400-2001-022.pdf:1.31MB
A numerical simulation code for the TRUEX (Transuranium Extraction) process was developed. Concentration profiles of americium and europium were calculated for some experiments of the counter current extraction system those were carried out in CPF (Chemical Processing Facility) by using the code. Calculation profiles were in agreement with the experimental results. Operational conditions were also examinted for the americium recovery experiment by the TRUEX process carried out in the Plutonium Fuel Center. It was shown that lowering the concentration of nitric acid in the scrub solution and decreasing the flow rate of solvent and strip solution was effective for improving the performance of the stripping step and reducing the volume of the waste solution. In order to find the optimum conditions for various experiments, this simulation code was modified to calculate the concentration profiles of other metal elements such as zirconium and iron and the effect of oxalic acid on the extraction behavior of the metal elements. The calculated concentration profiles of americium and europium were varied by this modification. In the experiment at CPF, the calculations were carried out to obtain recovery ratio of americium in the product stream with the amount of oxalic acid added to the process. This calculation result showed that it was possible to improve the performance of decontamination of fission products by increasing oxalic acid concentration added to the process. The calculation was also carried out for finding the optimum conditions of oxalic acid concentration added to the europium recovery process.
Watanabe, Masayuki; Tatsugae, Ryozo*; *; Morita, Yasuji; Kubota, Masumitsu
JAERI-Research 99-034, 55 Pages, 1999/05
JAERI-Research-99-034.pdf:1.7MB
no abstracts in English
Watanabe, Masayuki; Morita, Yasuji; Kubota, Masumitsu*; Tatsugae, Ryozo*
Radiochimica Acta, 87(3-4), p.115 - 119, 1999/00
no abstracts in English
Sakurai, Tsutomu; ; ; Komaki, Yoshihide
Journal of Nuclear Science and Technology, 32(7), p.664 - 670, 1995/07
Times Cited Count：4 Percentile：43.23(Nuclear Science & Technology)no abstracts in English
Shirahashi, Koichi; Morita, Yasuji; Kubota, Masumitsu
JAERI-Research 95-012, 34 Pages, 1995/03
JAERI-Research-95-012.pdf:0.84MB
no abstracts in English
*; Shirahashi, Koichi; Kubota, Masumitsu
JAERI-Research 95-011, 72 Pages, 1995/03
JAERI-Research-95-011.pdf:1.77MB
no abstracts in English
*; Morita, Yasuji; Kubota, Masumitsu
JAERI-M 90-168, 28 Pages, 1990/10
no abstracts in English
; ; ; Sakurai, Satoshi;
JAERI-M 90-161, 41 Pages, 1990/09
no abstracts in English
*; Morita, Yasuji; Kubota, Masumitsu
JAERI-M 90-023, 33 Pages, 1990/02
no abstracts in English
Morita, Yasuji; Kubota, Masumitsu
JAERI-M 89-139, 19 Pages, 1989/10
no abstracts in English
; *;
Journal of Nuclear Science and Technology, 13(6), p.321 - 326, 1976/06
Times Cited Count：7no abstracts in English
; *; *; *
JAERI-M 6106, 31 Pages, 1975/04
no abstracts in English
Sasaki, Yuji; Tsubata, Yasuhiro; Morita, Keisuke; Shirasu, Noriko; Shimazaki, Shoma; Kitatsuji, Yoshihiro
no journal, ,
no abstracts in English
