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-hexaoctyl nitrilotriacetamide (HONTA) using mixer-settler extractors in a hot cellBan, Yasutoshi; Suzuki, Hideya*; Hotoku, Shinobu; Tsubata, Yasuhiro
Solvent Extraction Research and Development, Japan, 31(1), p.1 - 11, 2024/00
A demonstration test was performed to separate minor actinides (MA; Am and Cm) by -hexaoctyl nitrilotriacetamide (HONTA) as an extractant using mixer-settler extractors installed in a hot cell. A high-level liquid waste containing MA, and rare earths (RE; Y, La, Nd, and Eu) was used as the feed. HONTA diluted to 0.05 mol/dm
in 
-dodecane was fed as the organic phase, and a part of the organic phase was reused without solvent regeneration. HONTA effectively extracted MA, whereas RE were less extractable. Consequently, the Y, La, Nd, and Eu ratios distributed to a RE fraction were 
99.9%, 99.2%, 61.8%, and 81.4%, respectively. The Am and Cm ratios distributed to an MA fraction were 86.8% and 74.7%, respectively, and a substantial amount of MA (0.12 g) was recovered in the MA fraction by the end of the cumulative duration of 40 h.
Kobayashi, Masaki*; Anh, L. D.*; Suzuki, Masahiro*; Kaneta-Takada, Shingo*; Takeda, Yukiharu; Fujimori, Shinichi; Shibata, Goro*; Tanaka, Arata*; Tanaka, Masaaki*; Oya, Shinobu*; et al.
Physical Review Applied (Internet), 15(6), p.064019_1 - 064019_10, 2021/06
Times Cited Count：4 Percentile：27.71(Physics, Applied)Takahashi, Atsushi*; Chiba, Mirei*; Tanahara, Akira*; Aida, Jun*; Shimizu, Yoshinaka*; Suzuki, Toshihiko*; Murakami, Shinobu*; Koarai, Kazuma; Ono, Takumi*; Oka, Toshitaka; et al.
Scientific Reports (Internet), 11(1), p.10355_1 - 10355_11, 2021/05
Times Cited Count：6 Percentile：41.49(Multidisciplinary Sciences)Hayashi, Makoto*; Okido, Shinobu*; Suzuki, Hiroshi
Quantum Beam Science (Internet), 4(2), p.18_1 - 18_12, 2020/06
-hexaoctyl nitrilotriacetamide (HONTA) using mixer-settler extractors in a hot cellBan, Yasutoshi; Suzuki, Hideya*; Hotoku, Shinobu; Tsutsui, Nao; Tsubata, Yasuhiro; Matsumura, Tatsuro
Solvent Extraction and Ion Exchange, 37(7), p.489 - 499, 2019/11
Times Cited Count：15 Percentile：52.81(Chemistry, Multidisciplinary)A continuous counter-current experiment to separate minor actinides (MAs: Am and Cm) was performed with -hexaochyl nitrilotriacetamide (HONTA) as an extractant. Nitric acid of 0.08 M (mol/dm) containing MAs and rare earths (REs) recovered from high-level waste was used as the Feed, and the experiment was conducted for 14 h. The ratios of Am and Cm recovered into the MA fraction measured 94.9% and 78.9%, respectively. HONTA hardly extracted Y, La, and Eu in the Feed (99.9% for Y, 99.9% for La, and 96.7% for Eu), most of which were distributed to the RE fraction. A portion of Nd was extracted by HONTA, and consequently the ratio of Nd in the RE fraction was 83.5%. The concentrations of MAs and some REs in each stage were calculated using a simulation code, and the results are consistent with the experimental values. This code indicates that the ratios of MAs in the MA fraction and REs in the RE fraction could be 
99% by optimizing separation conditions.
-tetradodecyldiglycolamide (TDdDGA) by using mixer-settler extractors in a hot cellBan, Yasutoshi; Suzuki, Hideya; Hotoku, Shinobu; Kawasaki, Tomohiro*; Sagawa, Hiroshi*; Tsutsui, Nao; Matsumura, Tatsuro
Solvent Extraction and Ion Exchange, 37(1), p.27 - 37, 2019/00
Times Cited Count：21 Percentile：65.06(Chemistry, Multidisciplinary)A continuous counter-current experiment using TDdDGA was performed using mixer-settler extractors installed in a hot cell. Nitric acid containing minor actinides (MAs: Am and Cm), rare earths (REs: Y, La, Nd, and Eu), and other fission products (Sr, Cs, Zr, Mo, Ru, Rh, and Pd) was fed to the extractor. TDdDGA effectively extracted MAs and REs from the feed, while other fission products were barely extracted. The extracted MAs and REs were back-extracted by bringing them in contact with 0.02 mol/dm nitric acid, and they were collected as the MA-RE fraction. The proportions of MA and RE in the MA-RE fraction were 98% and 86%, respectively. These results demonstrated the applicability of TDdDGA as an extractant for MAs and REs.
Sakamoto, Shoya*; Wakabayashi, Yuki*; Takeda, Yukiharu; Fujimori, Shinichi; Suzuki, Hakuto*; Ban, Yoshisuke*; Yamagami, Hiroshi; Tanaka, Masaaki*; Oya, Shinobu*; Fujimori, Atsushi*
Physical Review B, 95(7), p.075203_1 - 075203_5, 2017/02
Times Cited Count：9 Percentile：42.75(Materials Science, Multidisciplinary)
-dialkylamides using multistage mixer-settler extractorsBan, Yasutoshi; Hotoku, Shinobu; Tsutsui, Nao; Suzuki, Asuka; Tsubata, Yasuhiro; Matsumura, Tatsuro
Procedia Chemistry, 21, p.156 - 161, 2016/12
Times Cited Count：5 Percentile：94.32(Chemistry, Inorganic & Nuclear)A continuous counter-current experiment was carried out to demonstrate the validity of a process using -dialkylamides for recovering U and Pu. This process consisted of two cycles, and the 1st cycle and the 2nd cycle employed -di(2-ethylhexyl)-2,2-dimethylpropanamide and -di(2-ethylhexyl)butanamide as extractants, respectively. The feed solution for the 1st cycle was 5.1 mol/dm (M) nitric acid containing 0.92 M U, 1.6 mM Pu, and 0.6 mM Np. The raffinate collected in the 1st cycle was used as the feed for the 2nd cycle. The ratios of U recovered in the U fraction and U-Pu fraction were 99.1% and 0.8%, respectively. The ratio of Pu recovered in the U-Pu fraction was 99.7%. The concentration ratio of U with respect to Pu in the U-Pu fraction was 9, and this indicated that Pu was not isolated. The decontamination factor of U with respect to Pu in the U fraction was obtained as 4.5
10
. These results supported the validity of the proposed process.
Ban, Yasutoshi; Hotoku, Shinobu; Tsutsui, Nao; Suzuki, Asuka; Matsumura, Tatsuro
Proceedings of 5th International Conference on Asian Nuclear Prospects 2016 (ANUP 2016) (CD-ROM), 2 Pages, 2016/10
A continuous counter-current experiment was conducted using mixer-settler extractors installed in a hot cell. -Di(2-ethylhexyl)-2,2-dimethylpropanamide (DEHDMPA) was used as the extractant for U. The experimental results showed that DEHDMPA can effectively extract U from nitric acid, and the recovery of U in the U fraction was obtained as 99.6%.
Suzuki, Asuka; Hotoku, Shinobu; Ban, Yasutoshi; Tsutsui, Nao; Tsubata, Yasuhiro; Matsumura, Tatsuro
Proceedings of 5th International Conference on Asian Nuclear Prospects 2016 (ANUP 2016) (CD-ROM), 2 Pages, 2016/10
The Japan Atomic Energy Agency (JAEA) conducts extensive research and development (R&D) activities toward the development of aqueous separation processes for spent nuclear fuel at the Nuclear Fuel Cycle Safety Engineering Research Facility-Back-end Fuel Cycle Key Element Research Facility (NUCEF-BECKY). BECKY is equipped with three hot cells, several glove boxes, and fume hoods. One of the hot cells, called the process cell, contains bench scale spent fuel test equipment used for U, Pu, and other spent fuel material. In this study, we describe an equipment used for aqueous separation processes in the process cell.
Sn content in spent nuclear fuel sampleAsai, Shiho; Toshimitsu, Masaaki; Hanzawa, Yukiko; Suzuki, Hideya; Shinohara, Nobuo; Inagawa, Jun; Okumura, Keisuke; Hotoku, Shinobu; Kimura, Takaumi; Suzuki, Kensuke*; et al.
Journal of Nuclear Science and Technology, 50(6), p.556 - 562, 2013/06
Times Cited Count：11 Percentile：64.2(Nuclear Science & Technology)The Sn content in a spent nuclear fuel solution was determined by ICP-MS for its inventory estimation in high-level radioactive waste. An irradiated UO
fuel was used as a sample to evaluate the reliability of the methodology. Prior to the measurement, Sn was separated from Te, which causes major isobaric interference in the determination of Sn content, along with highly radioactive coexisting elements using an anion-exchange column. The absence of counts attributed to Te in the Sn-containing effluent indicates that Te was completely removed. After washing, Sn retained on the column was readily eluted with 1 M HNO
. The isotope ratios of Sn were successfully determined and showed good agreement with those obtained through ORIGEN2 calculations. The results reported in this paper are the first experimental values of Sn content in the spent nuclear fuel solution originating in spent nuclear fuel irradiated at a nuclear power plant in Japan.
Se and 
Cs in spent nuclear fuel for inventory estimation of high-level radioactive wastesAsai, Shiho; Hanzawa, Yukiko; Okumura, Keisuke; Shinohara, Nobuo; Inagawa, Jun; Hotoku, Shinobu; Suzuki, Kensuke*; Kaneko, Satoru*
Journal of Nuclear Science and Technology, 48(5), p.851 - 854, 2011/05
Times Cited Count：25 Percentile：86.49(Nuclear Science & Technology)Nakajima, Kohei; Suzuki, Yoshio; Teshima, Naoya; Sugimoto, Shinichiro*; Yoshimura, Shinobu*; Nakajima, Norihiro
Zen NEC C&C Shisutemu Yuza Kai Heisei-20-Nendo Rombunshu (CD-ROM), 13 Pages, 2009/02
Grid computing environment is equipped with a lot of tools to manage jobs and computers. Thereby, user can use the computers without directly access. However, user has to acquire usage of these tools even when user does an easy job because all usages of these tools are peculiar to the grid base. A lot of users think that the grid is difficult even though these tools exist. Then, we developed script generator API to make the job script. These settings were made easy by this API in the user application. In this paper, the outline of this API and the adjustment to the application are described.
Miyamura, Tomoshi*; Arai, Kentaro*; Mimura, Yasunari*; Yoshimura, Shinobu*; Suzuki, Yoshio
Keisan Kogaku Koenkai Rombunshu, 12(2), p.655 - 658, 2007/05
ADVENTURE_Opt is one of the software modules in the ADVENTURE System, which is an open source software system for computational mechanics. The system is designed for conducting large-scale analysis and design. ADVENTURE_Opt can conduct optimization of artifacts using an optimization algorithm such as the Real coded GA, and the finite element analyses are conducted for evaluating an objective function. In this paper, the ADVENTURE_Opt is modified for using the ITBL environment, which is a grid-environment developed in the national project in Japan. In the computation using the ADVENTURE_Opt, conducting the finite element analyses is the most time consuming. In the present implementation, this computation is conducted in the ITBL environment and the other parts are conducted on a personal computer. The ITBL client API library is used for implementing the system.
Ishikawa, Nobuyuki; *; ; Suzuki, Katsuo
Proc. of AIR & IHAS '97, p.213 - 225, 1997/00
no abstracts in English
; Uramoto, Toshimasa; Fukushima, Masao; ; ; ;
Proc. of the 3rd Asian Symp. on Research Reactor, p.285 - 292, 1991/00
no abstracts in English
; ; ; Watanabe, Hiroyuki; ;
JAERI-M 90-196, 45 Pages, 1990/11
no abstracts in English
; ; Watanabe, Hiroyuki; ; ;
JAERI-M 89-043, 35 Pages, 1989/03
no abstracts in English
; ; ; *; ; Itami, Hiroharu
JAERI-M 88-199, 39 Pages, 1988/10
no abstracts in English
; *; ; ;
JAERI-M 87-041, 45 Pages, 1987/03
no abstracts in English
