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Journal Articles

Complex formation of light and heavy lanthanides with DGA and DOODA, and its application to mutual separation in DGA-DOODA extraction system

Nomizu, Daiki; Sasaki, Yuji; Kaneko, Masashi; Matsumiya, Masahiko*; Katsuta, Shoichi*

Journal of Radioanalytical and Nuclear Chemistry, 331(3), p.1483 - 1493, 2022/03

https://doi.org/10.1007/s10967-022-08204-5

Times Cited Count：4 Percentile：76.47(Chemistry, Analytical)

We studied the successive formation of water soluble DGA (diglycolamide) and DOODA (dioxaoctanediamide) for the mutual separation of Ln in this extraction system. TODGA (tetraoctyl-diglycolamide) and DOODA(C8) (tetraoctyl-dioxaoctanediamide) have the opposite trend to extract light and heavy Ln through Ln-patterns. Metal-complexes of two folding Ln ions with water-soluble DOODA and three folding with DGA are found and their observed formation constants are calculated. The suitable separation condition (aqueous phase: 30 mM DOODA(C2) in 1 M nitric acid, organic phase: 0.1 M TODGA in n-dodecane) of multi-stage extraction (10 10) is conducted. From the present work, it is clear that La, Pr and Nd are mainly present in aqueous phase, instead Sm-Dy exist in the organic phase.

Journal Articles

Hydrogenation of 1 $_{2}$ -type AlNi $_{3}$ alloy at high pressure and temperature

Endo, Naruki*; Saito, Hiroyuki; Machida, Akihiko; Katayama, Yoshinori

Journal of Alloys and Compounds, 645(Suppl.1), p.S61 - S63, 2015/10

https://doi.org/10.1016/j.jallcom.2015.01.200

Times Cited Count：0 Percentile：0.01(Chemistry, Physical)

JAEA Reports

Investigation of release behavior of volatile ruthenium species from thermal decomposition of ruthenium nitrosylnitrate

Abe, Hitoshi; Masaki, Tomoo; Amano, Yuki; Uchiyama, Gunzo

JAEA-Research 2014-022, 12 Pages, 2014/11

JAEA-Research-2014-022.pdf:1.03MB

To contribute safety evaluation of boiling and drying accident of high active liquid waste (HALW) in fuel reprocessing plant, release behavior of Ru, which was considered as an important nuclide for evaluating public dose from the volatile viewpoint, has been investigated. It has been reported that release of Ru becomes conspicuously after HALW is dried up. In this work, to grasp the release behavior of Ru, release ratio of Ru with thermal decomposition of Ru nitrate, which would be in the dried HALW, was measured and release rate constant of Ru from the nitrate was estimated. It was found that the calculation result of release rate of Ru from the nitrate with rise of temperature by using the constant could well simulate the result acquired from the beaker-scale experiment.

Journal Articles

Mechanical properties of weldments using irradiated stainless steel welded by the laser method for ITER blanket replacement

Yamada, Hirokazu*; Kawamura, Hiroshi; Nagao, Yoshiharu; Takada, Fumiki; Kono, Wataru*

Journal of Nuclear Materials, 355(1-3), p.119 - 123, 2006/09

https://doi.org/10.1016/j.jnucmat.2006.04.010

Times Cited Count：5 Percentile：36.24(Materials Science, Multidisciplinary)

In this study, the bending properties of welding joint of irradiated material and un-irradiated material (irradiated/un-irradiated joints) were investigated using SS316LN-IG, which is the candidate material for the cooling pipe of ITER. The results of this study showed that the bending position of joints using un-irradiated material was un-irradiated part and that the bending position of irradiated/irradiated joints was fusion area or HAZ (heat affected zone). Although the bending position of joints was different bor the combination pattern between irradiated and un-irradiated materials, the bending strength of joint was almost same. Additionally, it is confirmed that bending strength did not depend on the combination pattern between the irradiated and un-irradiated materials, nor on the relationship between the heat input direction and the bending load direction.

Journal Articles

Manufacturing study and trial fabrication of radial plate for ITER toroidal field coil

Abe, Kanako*; Nakajima, Hideo; Hamada, Kazuya; Okuno, Kiyoshi; Kakui, Hideo*; Yamaoka, Hiroto*; Maruyama, Naoyuki*

IEEE Transactions on Applied Superconductivity, 16(2), p.807 - 810, 2006/06

https://doi.org/10.1109/TASC.2006.873261

Times Cited Count：12 Percentile：51.46(Engineering, Electrical & Electronic)

no abstracts in English

Journal Articles

Effects of nitrogen on the mechanical properties of 316LN stainless steels

Ishio, Kotaro*; Nakajima, Hideo

Tetsu To Hagane, 92(2), p.90 - 96, 2006/02

http://ci.nii.ac.jp/naid/110003482898

no abstracts in English

Journal Articles

Effects of Nitrogen, Niobium, Phosphorous and Carbon on the mechanical properties of aged 316LN stainless steels at the cryogenic temperature, 4K

Ishio, Kotaro*; Hamada, Kazuya; Nakajima, Hideo

Tetsu To Hagane, 92(1), p.30 - 35, 2006/01

http://ci.nii.ac.jp/naid/110002973201

no abstracts in English

JAEA Reports

An Investigation on natural gas utilization development in Japan

Suzuki, Takayoshi*

JAERI-Review 2005-042, 38 Pages, 2005/09

JAERI-Review-2005-042.pdf:3.13MB

After the Basic Plan on Energy was determined, a set of policy measures as proposed in order to accelerate a shift to natural gas: development of domestic infrastructure of natural gas utilization, making effort to lower and stabilize import prices of LNG, support for introducing gas cogeneration, etc. Also the Program to Achieve Kyoto-Protocol Target proposes to promote the natural gas shift. In these circumstances, this report summarizes the results of investigation on natural gas resources, LNG import, domestic infrastructure of natural gas utilization, current and future prices of natural gas, the development of natural gas utilization technologies, and new types of fuel for end-use. Natural gas is expected more abundant than petroleum, therefore Japan has increased its import. In addition, its prices might be lower in the future in comparison with petroleum prices. Natural gas will take more important role as a primary energy source in Japan under the support program by the Government.

Journal Articles

The Effect of neutron irradiation on mechanical properties of YAG laser weldments using previously irradiated material

Yamada, Hirokazu*; Kawamura, Hiroshi; Tsuchiya, Kunihiko; Kalinin, G.*; Nagao, Yoshiharu; Takada, Fumiki; Nishikawa, Masahiro*

Journal of Nuclear Materials, 340(1), p.57 - 63, 2005/04

https://doi.org/10.1016/j.jnucmat.2004.10.117

Times Cited Count：5 Percentile：35.66(Materials Science, Multidisciplinary)

This study was performed to clear the effect of neutron re-irradiation on mechanical properties to welding material un-irradiated and irradiated stainless steel. The effect of re-irradiation to these weldaments were evaluated by tensile tests, metallographical observation and hardness test. The result of tensile tests shows that ultimate tensile strength of all joints specimen were almost similar, 0.2% yield strength and total elongation were depend on the irradiation damage and weldaments or not. Therefore, fracture mechanism was not change by re-irradiation. However, brittlement of material was depend on irradiation damage and the property of deformation was sensitive by the effect of irradiation damage or the effect of welding heat.

Journal Articles

Stability of lanthanide oxides in LiCl-KCl eutectic melt

Hayashi, Hirokazu; Minato, Kazuo

Journal of Physics and Chemistry of Solids, 66(2-4), p.422 - 426, 2005/02

https://doi.org/10.1016/j.jpcs.2004.06.054

Times Cited Count：34 Percentile：75.63(Chemistry, Multidisciplinary)

Stability of lanthanide sesquioxides (LnO; Ln=La, Nd, Gd) in LiCl-KCl eutectic melt is studied. Some lanthanide oxides have been pointed out to form oxide chlorides (LnOCl) in the chloride melts, according to the reaction, LnO + 2Cl = 2LnOCl +O $^{2-}$ . Equilibrium of the reaction for Ln = La, Nd, Gd in LiCl-KCl eutectic melt were studied. Entire LaO and a part of NdO converted to LaOCl and NdOCl respectively, though GdO remained with a trace amount of GdOCl for 2wt % of LnO in LiCl-KCl eutectic melt. The equilibrium depends on the free energies of formation of the solid compounds, LnO and LnOCl, and that of oxide ion (O $^{2-}$ ) in the melt. We derive the chemical potential of the oxide ion from the equilibrium using the reported thermochemical data of LnO and LnOCl.

Journal Articles

Effect of DTPA on the extractions of Actinides(III) and Lanthanides(III) from nitrate solution into TODGA/-dodecane

Apichaibukol, A.; Sasaki, Yuji; Morita, Yasuji

Solvent Extraction and Ion Exchange, 22(6), p.997 - 1011, 2004/12

https://doi.org/10.1081/SEI-200037727

Times Cited Count：41 Percentile：71.39(Chemistry, Multidisciplinary)

no abstracts in English

Journal Articles

Extraction of Am(III) and Lanthanide(III) ions from HNO $_{3}$ solutions using -dimethyl--diphenylpyridine-2,6-dicarboxyamide

Shimada, Asako; Yaita, Tsuyoshi; Narita, Hirokazu; Tachimori, Shoichi; Kimura, Takaumi; Okuno, Kenji*; *

Solvent Extraction Research and Development, Japan, 11, p.1 - 10, 2004/04

The distribution ratio () of Am(III) and lighter Ln(III) in the extraction with -dimethyl--diphenylpyridine-2,6-dicarboxyamide(DMDPhPDA) from HNO $_{3}$ solutions were determined. The D's increased with an increase of HNO $_{3}$ concentration. Additionally, separation of Am(III) from Ln(III) were confirmed for all the HNO $_{3}$ concentration range (S.F.=(D $_{Am}$ /D $_{Ln}$ )). From 4 M HNO $_{3}$ solution with 0.5 M DMDPhPDA CHCl $_{3}$ solution, the 's of Am(III), Eu(III) and Nd(III) were 1.3, 0.25 and 0.24, respectively. This result suggests that Am(III) can be separated from Eu and Nd in the higher HNO $_{3}$ concentration region than that has been reported so far. These 's value and the S.F. were reproduced in the extraction from the metal concentration range from 10 $^{-1}$ M order to 10 $^{-8}$ M.

Journal Articles

Characterization of 316L(N)-IG SS joint produced by hot isostatic pressing technique

Nakano, Junichi; Miwa, Yukio; Tsukada, Takashi; Kikuchi, Masahiko; Kita, Satoshi; Nemoto, Yoshiyuki; Tsuji, Hirokazu; Jitsukawa, Shiro

Journal of Nuclear Materials, 307-311(Part2), p.1568 - 1572, 2002/12

https://doi.org/10.1016/S0022-3115(02)00965-0

Times Cited Count：12 Percentile：60.73(Materials Science, Multidisciplinary)

Type 316LN stainless steel of the international thermonuclear experimental reactor (ITER) Grade (316LN-IG SS) is being considered for the first wall/ blanket component. Hot isostatic pressing (HIP) technique is expected for the fabrication of module. To evaluate the integrity and susceptibility to stress corrosion cracking (SCC) of HIPed 316LN-IG SS, tensile tests in vacuum and slow strain rate tests (SSRT) in high temperature water were performed. Specimen with the HIPed joint shows no deterioration of the tensile strength and susceptibility to SCC in oxygenated water. Thermally sensitized specimen with the HIPed joint was low susceptible to SCC in creviced environment. It is concluded that the strength at joint location is as high as that at the base alloy and the joint interface appears integrity.

Journal Articles