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Journal Articles

Development of a new extractant and a new extraction process for minor actinide separation

Morita, Yasuji; Sasaki, Yuji; Asakura, Toshihide; Kitatsuji, Yoshihiro; Sugo, Yumi; Kimura, Takaumi

IOP Conference Series; Materials Science and Engineering, 9, p.012057_1 - 012057_11, 2010/05

 Times Cited Count:7 Percentile:92.29

The authors have developed a new type of extractant for Am and Cm, ${it N,N,N',N'}$-tetraoctyl-diglycolamide (TODGA), which gives very high distribution ratio at relatively high nitric acid concentration. To apply such a new extractant to the separation process for Am and Cm from HLLW, many criteria should be investigated and satisfied; e.g., separability against fission products (FP), chemical and radiolytic stability, extraction capacity, compatibility with hydrocarbon diluents, and so on. From a viewpoint of extraction capacity, TODGA is modified to ${it N,N,N',N'}$-tetradodecyl-diglycolamide (TDdDGA). Since TDdDGA extract Zr and Pd, effective masking agents for them were examined and selected. With those achievements, a counter-current extraction test with 0.1 M TDdDGA in n-dodecane was carried out using a small-scale mixer-settler and simulated solution of HLLW. As results of the test, a very high recovery of Am, more than 99.96%, was obtained and good separation from FP was observed.

Journal Articles

Counter-current extraction and separation of Nd from Sr, Zr and Pd by TDdDGA, ${it N,N,N',N'}$-tetradodecyl-diglycolamide

Sasaki, Yuji; Asakura, Toshihide; Kitatsuji, Yoshihiro; Morita, Yasuji; Kimura, Takaumi

Proceedings of 10th OECD/NEA Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation (CD-ROM), 6 Pages, 2010/00

Diglycolamide, DGA, compounds have the strong extractability with trivalent, tetravalent and hexavalent actinides (An) from nitric acid to n-dodecane. Since DGA connecting with the long alkyl chain, TDdDGA (${it N,N,N',N'}$-tetradodecyl-diglycolamide), has the high extraction capacity and suppresses to form the third phase with Nd, we used TDdDGA to demonstrate the counter-current extraction, prior to the hot test. In this experiment we use four elements, i.e., Sr, Pd, Zr and Nd, as the typical fission products and a representative ion of An(III) and lanthanides, to confirm the extraction and the separation properties, these four elements are extractable by TDdDGA. After determination of the optimum condition on the extraction and separation of Nd from other elements by the calculation using D values, we perform the counter-current extraction using the mixer-settler equipment.

Journal Articles

Chemical separation of actinides from high level radioactive liquid waste using diglycolamide (DGA) compounds

Sasaki, Yuji; Kitatsuji, Yoshihiro; Sugo, Yumi; Asakura, Toshihide; Kimura, Takaumi

Proceedings of International Conference on Advanced Nuclear Fuel Cycles and Systems (Global 2007) (CD-ROM), p.1117 - 1120, 2007/09

An innovative chemical separation process for the treatment of high level radioactive liquid waste (HLW) has been developed in our laboratory. There are two main stages in this process. The diglycolamide (DGA) compounds employed for TRU recovery have several advantages, (1) carbon, hydrogen, oxygen and nitrogen atoms in their structures and gasification by combustion, (2) easy synthesis, (3) neutral and tridentate ligands, and (4) strong extraction ability with An from HNO$$_{3}$$). DGA compounds with the different structures can be obtained by attachment of the different alkyl groups to amidic N atoms, i.e., tetraoctyl-diglycolamide (TODGA), tetradodecyl-diglycolamide (TDdDGA), tetrametyl-diglycolamide (TMDGA) and tetraetyl-diglycolamide (TEDGA). The utility of DGA compounds, which shows the different characters, is revealed and the flow-sheet based on the salt-free concept is exhibited in this paper.

Journal Articles

Atomic stereophotograph of intercalation compound Fe$$_{1/3}$$NbS$$_{2}$$

Guo, F. Z.*; Matsushita, Tomohiro*; Kobayashi, Keisuke*; Matsui, Fumihiko*; Kato, Yukako*; Daimon, Hiroshi*; Koyano, Mikio*; Yamamura, Yasuhisa*; Tsuji, Toshihide*; Saito, Yuji

Journal of Applied Physics, 99(2), p.024907_1 - 024907_3, 2006/01

 Times Cited Count:8 Percentile:31.35(Physics, Applied)

Stereoatomscope was used to study the atomic arrangements of intercalation compound Fe$$_{1/3}$$NbS$$_{2}$$. The three-dimensional atomic arrangements around different kinds of atoms (Nb and Fe) are visualized by taking the photoelectron angular distribution (PEAD) patterns at clockwise and counterclockwise circularly polarized lights. Atomic distances between the emitters and the scatterers are obtained from the PEAD patterns by measuring the rotation angles of the forward focusing peaks. The applications of stereoatomscope to intercalation compound show the possibility to build an ultimate microscope for scientist.

Journal Articles

Photoemission and core-level absorption spectroscopy of Fe$$_{x}$$NbS$$_{2}$$

Saito, Yuji; Kobayashi, Keisuke*; Fujimori, Atsushi; Yamamura, Yasuhisa*; Koyano, Mikio*; Tsuji, Toshihide*; Katayama, Shinichi*

Journal of Electron Spectroscopy and Related Phenomena, 144-147, p.829 - 832, 2005/06

 Times Cited Count:5 Percentile:27.37(Spectroscopy)

no abstracts in English

Journal Articles

ITER activities in Japan

Tsunematsu, Toshihide; Seki, Masahiro; Tsuji, Hiroshi; Okuno, Kiyoshi; Kato, Takashi; Shibanuma, Kiyoshi; Hanada, Masaya; Watanabe, Kazuhiro; Sakamoto, Keishi; Imai, Tsuyoshi; et al.

Fusion Science and Technology, 42(1), p.75 - 93, 2002/07

 Times Cited Count:1 Percentile:10.15(Nuclear Science & Technology)

Japanese contributions to ITER Engineering Design Activity are presented, together with an introduction of the objectives and design of the ITER whose program have been carried out through the international collaboration by EU, Japan, Russian Federation and the USA. New technologies have been produced through the development, fabrication and testing of scalable models in the fields of superconducting magnet, reactor structure with vacuum vessel, high-heat-flux plasma facing component, neutral beam injector, high-power mm-wave generator and so on. As major contributions from Japan, development and testing results of a 13-T, 640-MJ, Nb$$_{3}$$Sn pulsed magnet, a 18-degree sector of vacuum vessel with a height of 15 m and a width of 9 m, CFC armors to CuCrZr cooling tube that withstood 20 MW/m$$^{2}$$, a 31 mA/cm$$^{2}$$ negative ion beam source, a 1-MeV beam-accelerator, a 1-MW 170-GHz gyrotron were described.

Journal Articles

Thermal expansion of neptunium-plutonium mixed oxides

Yamashita, Toshiyuki; ; Tsuji, Toshihide*; *

Journal of Alloys and Compounds, 271-273, p.404 - 407, 1998/00

 Times Cited Count:9 Percentile:55.14(Chemistry, Physical)

no abstracts in English

Journal Articles

Electrical conductivity of uranium-neptunium mixed oxides

Yamashita, Toshiyuki; *; Tsuji, Toshihide*; Kato, Tetsuya*; *; Iwashita, Mitsushige*

Journal of Alloys and Compounds, 271-273, p.400 - 403, 1998/00

 Times Cited Count:4 Percentile:39.25(Chemistry, Physical)

no abstracts in English

Journal Articles

Thermal expansions of NpO$$_{2}$$ and some other actinide dioxides

Yamashita, Toshiyuki; Shirasu, Noriko; Tsuji, Toshihide*; *

Journal of Nuclear Materials, 245(1), p.72 - 78, 1997/00

 Times Cited Count:103 Percentile:98.56(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Thermal expansion of neptunium-uranium mixed oxides

Yamashita, Toshiyuki; Shirasu, Noriko; Tsuji, Toshihide*; Kato, Tetsuya*

Journal of Nuclear Materials, 247, p.90 - 93, 1997/00

 Times Cited Count:50 Percentile:94.73(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Phase relations of the uranium-neptunium-oxygen system

Yamashita, Toshiyuki; ; Ouchi, Kinji; Muromura, Tadasumi; Tsuji, Toshihide*; *; Kato, Tetsuya*

Journal of Alloys and Compounds, 213-214, p.375 - 377, 1994/00

 Times Cited Count:12 Percentile:66.85(Chemistry, Physical)

no abstracts in English

Journal Articles

Electrical conductivity and defect structure of lanthanum-doped (U,Pu)O$$_{2pm x}$$

Tsuji, Toshihide*; *; Yamashita, Toshiyuki; Fujino, Takeo*

Journal of Alloys and Compounds, 213-214, p.378 - 380, 1994/00

 Times Cited Count:1 Percentile:25.32(Chemistry, Physical)

no abstracts in English

Journal Articles

Study on diffusion of iron in iron telluride by Moessbauer spectroscopy and reaction between iron-chromium alloy and tellurium

; Tsuji, Toshihide*; *

Defect Diffus. Forum, 95-98, p.887 - 892, 1993/00

no abstracts in English

Journal Articles

Diffusion of iron in $$beta$$-iron telluride(Fe$$_{1.12}$$Te) by Moessbauer spectroscopy and tracer method

; Tsuji, Toshihide*; *

Journal of Nuclear Materials, 203, p.172 - 178, 1993/00

 Times Cited Count:3 Percentile:38.1(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Diffusion of iron in $$delta$$-iron telluride(Fe$$_{0.743}$$Te) by Moessbauer spectroscopy

; Tsuji, Toshihide*; *

Journal of Nuclear Materials, 203, p.179 - 185, 1993/00

 Times Cited Count:3 Percentile:38.1(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

High temperature electrical conductivity and conduction mechanism of (U,Pu)O$$_{2 pm x}$$ at low oxygen partial pressures

Fujino, Takeo*; Yamashita, Toshiyuki; Ouchi, Kinji; *; Tsuji, Toshihide*

Journal of Nuclear Materials, 202, p.154 - 162, 1993/00

 Times Cited Count:10 Percentile:72.15(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Kinetics and mechanism of telluride scale growth on iron

; Tsuji, Toshihide*; *

Journal of Nuclear Science and Technology, 29(1), p.68 - 77, 1992/01

no abstracts in English

Journal Articles

High temperature corrosion of iron chromium alloys by tellurium

; Tsuji, Toshihide*; *

Journal of Nuclear Science and Technology, 28(8), p.721 - 731, 1991/08

no abstracts in English

Journal Articles

Basic chemistry of severe accident of nuclear reactor

P.E.Potter*; Nakamura, Akio; Tsuji, Toshihide*

Nihon Genshiryoku Gakkai-Shi, 31(3), p.347 - 349, 1989/03

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

no abstracts in English

Oral presentation

Development of total recovery of TRU by diglycolamide-type compounds; Multi-stage separation test using mixer-settler

Asakura, Toshihide; Imaizumi, Hirobumi; Sasaki, Yuji; Kitatsuji, Yoshihiro; Morita, Yasuji; Kimura, Takaumi

no journal, , 

Total TRU separation technology using diglycolamide as an extraction solvent has been developed to apply it to the MA separation process of the spent FBR fuel reprocessing, etc. Separation tests were performed using Mixer-settlers. 1 M (mol dm$$^{-3}$$) nitric acid solution containing Nd, Sr, Zr, Pd, H$$_{2}$$O$$_{2}$$ and EDTA was used as the feed, and 0.1 M tetradodecyl diglycolamide / docecane was used as the extraction solvent. Only Nd was used to represent the trivalent cations such as Am, Cm and rare earthes. As the results, Nd was extracted from the feed and Sr was separated from Nd, highly effectively. Almost all of Zr and Pd were not extracted and transferred to raffinate, 3 % of Zr and 0.4 % of Pd, however, were transferred to the Nd product.

22 (Records 1-20 displayed on this page)