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Journal Articles

Minor actinides separation by ${it N,N,N',N',N'',N''}$-hexaoctyl nitrilotriacetamide (HONTA) using mixer-settler extractors in a hot cell

Ban, 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 ${it N,N,N',N',N'',N''}$-hexaochyl nitrilotriacetamide (HONTA) as an extractant. Nitric acid of 0.08 M (mol/dm$$^{3}$$) 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 $$geq$$99% by optimizing separation conditions.

Journal Articles

Extraction of trivalent rare earths and minor actinides from nitric acid with ${it N,N,N',N'}$-tetradodecyldiglycolamide (TDdDGA) by using mixer-settler extractors in a hot cell

Ban, 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$$^{3}$$ 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.

Journal Articles

Uranium and plutonium extraction by ${it N,N}$-dialkylamides using multistage mixer-settler extractors

Ban, 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 ${it N,N}$-dialkylamides for recovering U and Pu. This process consisted of two cycles, and the 1st cycle and the 2nd cycle employed ${it N,N}$-di(2-ethylhexyl)-2,2-dimethylpropanamide and ${it N,N}$-di(2-ethylhexyl)butanamide as extractants, respectively. The feed solution for the 1st cycle was 5.1 mol/dm$$^{3}$$ (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$$times$$10$$^{5}$$. These results supported the validity of the proposed process.

Journal Articles

A Continuous counter-current experiment for U extraction using DEHDMPA in a hot cell

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. ${it N,N}$-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%.

Journal Articles

Distribution behavior of neptunium by extraction with ${it N,N}$-dialkylamides (DEHDMPA and DEHBA) in mixer-settler extractors

Ban, Yasutoshi; Hotoku, Shinobu; Tsutsui, Nao; Tsubata, Yasuhiro; Matsumura, Tatsuro

Solvent Extraction and Ion Exchange, 34(1), p.37 - 47, 2016/01

 Times Cited Count:9 Percentile:29.47(Chemistry, Multidisciplinary)

The extraction properties of ${it N,N}$-di(2-ethylhexyl)-2,2-dimethylpropanamide (DEHDMPA) and ${it N,N}$-di(2-ethylhexyl)butanamide (DEHBA) for Np(V) and Np(VI) were studied by a batch method using various nitrate ion concentrations. The distribution ratios of Np(VI) obtained with DEHDMPA and DEHBA exceeded unity when the nitrate ion concentration was $$>$$3 mol/L. DEHDMPA and DEHBA barely extracted Np(V), and the maximum distribution ratios were 0.4 and 0.2 when DEHDMPA and DEHBA were used as extractants, respectively. A continuous counter-current experiment was performed to evaluate the behavior of Np in a process comprising two cycles. The ratio of Np recovered to the U fraction and U-Pu fraction were 63.7% and 29.1%, respectively. The behavior of Np suggested that the valence state of Np changed from Np(V) to Np(IV) or Np(VI) after the 1st experimental cycle. The recoveries of U and Pu to the U fraction stream and the U-Pu fraction stream were 99.9% and 99.8%, respectively.

Journal Articles

A Study on the application of ${it N,N}$-dialkylamides as extractants for U and Pu by continuous counter-current extractors

Ban, Yasutoshi; Hotoku, Shinobu; Tsubata, Yasuhiro; Tsutsui, Nao; Matsumura, Tatsuro

Proceedings of 21st International Conference & Exhibition; Nuclear Fuel Cycle for a Low-Carbon Future (GLOBAL 2015) (USB Flash Drive), p.1147 - 1152, 2015/09

Extraction properties of ${it N,N}$-di(2-ethylhexyl)-2,2-dimethylpropanamide (DEHDMPA), ${it N,N}$-di(2-ethylhexyl)butanamide (DEHBA), and some of their degradation products for the metal elements Zr, Mo, Ru, Rh, and Pd were studied using a single-stage batch method, and the results showed that the degradation products barely extracted these metal elements. Furthermore, separation performance of DEHDMPA and DEHBA for U and Pu in a continuous counter-current process was evaluated using a calculation code, and it was confirmed that the calculated values of U concentration in the U fraction and U and Pu concentrations in the U-Pu fraction were similar to those measured experimentally. These results supported the applicability of DEHDMPA and DEHBA as extractants for separation processes and the validity of the calculation code for estimating the separation performance of the process.

JAEA Reports

The Washing tests of degraded solvent by butylamine compounds

Kamei, Kazushige; Ito, Yoshinori*; Hotoku, Shinobu; Asakura, Toshihide; Watanabe, Makio; Mineo, Hideaki; Uchiyama, Gunzo

JAERI-Research 2001-026, 27 Pages, 2001/03

JAERI-Research-2001-026.pdf:1.18MB

no abstracts in English

JAEA Reports

None

Matsumoto, Shiro*

PNC TJ1609 97-002, 35 Pages, 1997/03

PNC-TJ1609-97-002.pdf:2.03MB

None

JAEA Reports

Outline of a fuel treatment facility in NUCEF

Sugikawa, Susumu; ; ; Nakazaki, Masato; Shirahashi, Koichi; ; *; *; Tsuji, Kenichi*; Tachimori, Shoichi; et al.

JAERI-Tech 97-007, 86 Pages, 1997/03

JAERI-Tech-97-007.pdf:3.27MB

no abstracts in English

JAEA Reports

Design, construction and tests of geometrically safe mixer settler

; Sugikawa, Susumu; ; Miyoshi, Yoshinori; Miyauchi, Masakatsu; Izawa, Naoki

JAERI-Tech 96-058, 28 Pages, 1997/01

JAERI-Tech-96-058.pdf:1.21MB

no abstracts in English

JAEA Reports

Extraction behavior of radionuclides in the first separation cycle in reprocessing

Uchiyama, Gunzo; Asakura, Toshihide; Hotoku, Shinobu; Watanabe, Makio; *; Fujine, Sachio

JAERI-Research 96-069, 49 Pages, 1997/01

JAERI-Research-96-069.pdf:1.75MB

no abstracts in English

Journal Articles

Most critical geometry of a fuel solution based on the transport boundary perturbation theory

Yamamoto, Toshihiro

Journal of Nuclear Science and Technology, 33(1), p.78 - 82, 1996/01

 Times Cited Count:1 Percentile:14.44(Nuclear Science & Technology)

no abstracts in English

Journal Articles

A New separation process of neptunium, technetium, plutonium and uranium using butyraldehydes as reductants in nuclear fuel reprocessing

Uchiyama, Gunzo; Asakura, Toshihide; Watanabe, Makio; Fujine, Sachio; Maeda, Mitsuru

Value Adding Through Solvent Extraction (Proc. of ISEC 96), 2, p.1291 - 1296, 1996/00

no abstracts in English

Journal Articles

Dissolution of plutonium dioxide by electrolytic oxidation method, II; Scaling-up experiments and purification of plutonium

Sakurai, Satoshi; Usuda, Shigekazu; ; Hirata, Masaru; ; Tachimori, Shoichi

Nihon Genshiryoku Gakkai-Shi, 35(2), p.147 - 154, 1993/02

no abstracts in English

Journal Articles

Study on accumulation of U(IV) in extraction-scrub columns of 30 vol% TBP-n$$cdot$$dodecane-U(VI)-HNO$$_{3}$$ system

; Tachimori, Shoichi; Usuda, Shigekazu; ; ; *

Solvent Extraction 1990, p.699 - 704, 1992/00

no abstracts in English

JAEA Reports

Effect of nonuniform concentration profile of plutonium in mixer settler on criticality of the Purex process

; Miyoshi, Yoshinori; Tachimori, Shoichi

JAERI-M 91-184, 31 Pages, 1991/11

JAERI-M-91-184.pdf:0.94MB

no abstracts in English

JAEA Reports

None

Nomura, Kazunori; ; Sakai, Toshiyuki*; *;

PNC TN8410 91-180, 51 Pages, 1991/06

PNC-TN8410-91-180.pdf:1.06MB

None

JAEA Reports

None

Gonda, Kozo; *; *; *

PNC TN841 80-01, 128 Pages, 1980/01

PNC-TN841-80-01.pdf:2.95MB

no abstracts in English

JAEA Reports

None

Gonda, Kozo; Nemoto, Takeshi; Yasu, Shozo*; *

PNC TN841 79-05, 32 Pages, 1979/02

PNC-TN841-79-05.pdf:0.85MB

no abstracts in English

Oral presentation

R&D of MA separation processes for P&T system using ADS, 3; Counter-current continuous extraction tests of MA-Ln recovery process

Urabe, Shunichi; Tsubata, Yasuhiro; Suzuki, Hideya; Shibata, Mitsunobu; Kurosawa, Tatsuya; Kawasaki, Tomohiro; Matsumura, Tatsuro

no journal, , 

JAEA continues to carry out the development of the ADS (Double-strata). Mutual separation of MA and Ln is important for the development of the partitioning process. TDdDGA was performed using a mixer-settler equipment for the development of the separation process for MA. TDdDGA has a high extraction capacity. TDdDGA consists of C, H, O and N atoms (the CHON-principle). In this experiment, the feed solution as simulated HLLW contained fourteen elements. The results of the counter-current test showed that Am was extracted and was recovered in a high yield.

28 (Records 1-20 displayed on this page)