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On the adsorption and reactivity of element 114, flerovium

Yakushev, A.*; Lens, L.*; D$"u$llmann, Ch. E.*; Khuyagbaatar, J.*; J$"a$ger, E.*; Krier, J.*; Runke, J.*; Albers, H. M.*; 浅井 雅人; Block, M.*; et al.

Frontiers in Chemistry (Internet), 10, p.976635_1 - 976635_11, 2022/08

 被引用回数:8 パーセンタイル:88.78(Chemistry, Multidisciplinary)



Improvement in flow-sheet of extraction chromatography for trivalent minor actinides recovery

渡部 創; 先崎 達也; 柴田 淳広; 野村 和則; 竹内 正行; 中谷 清治*; 松浦 治明*; 堀内 勇輔*; 新井 剛*

Journal of Radioanalytical and Nuclear Chemistry, 322(3), p.1273 - 1277, 2019/12

 被引用回数:3 パーセンタイル:35.01(Chemistry, Analytical)

Extraction chromatography flow-sheet employing octyl(phenyl)-$$N,N$$-diisobutylcarbonoylmethylphosphine oxide (CMPO) and $$bis$$(2-ethylhexyl) hydrogen phosphate (HDEHP) extractants for trivalent minor actinide recovery was modified to improve column separation performance. Excellent trivalent minor actinides recovery performance was obtained by column separation experiments on nitric acid solution containing the trivalent minor actinides and representative fission product elements, i.e. recovery yields $$>$$ 93% with sufficient decontamination factors against the fission products. Those are the best performance which we have ever obtained by experiments inside hot cell.


Online chemical adsorption studies of Hg, Tl, and Pb on SiO$$_{2}$$ and Au surfaces in preparation for chemical investigations on Cn, Nh, and Fl at TASCA

Lens, L.*; Yakushev, A.*; D$"u$llmann, Ch. E.*; 浅井 雅人; Ballof, J.*; Block, M.*; David, H. M.*; Despotopulos, J.*; Di Nitto, A.*; Eberhardt, K.*; et al.

Radiochimica Acta, 106(12), p.949 - 962, 2018/12


 被引用回数:6 パーセンタイル:56.14(Chemistry, Inorganic & Nuclear)

半減期4$$sim$$49秒の短寿命同位体を用いて、水銀(Hg), タリウム(Tl), 鉛(Pb)の単一原子レベルでのSiO$$_{2}$$及びAu表面への固体吸着挙動をオンライン気相実験により調べた。超重元素Cn, Nh, Flの吸着エンタルピー測定のためのモデル実験として実施した。短寿命同位体はドイツ重イオン研究所の反跳核分離装置TASCAを用いて生成・分離した。生成核はヘリウムガス中に捕集された後、SiO$$_{2}$$あるいはAuで表面を覆われたSi検出器で作製されたガスクロマトグラフィーカラムへと導入した。短寿命Tl及びPb同位体は室温においてSiO$$_{2}$$表面に吸着し、Si検出器で測定することに成功した。一方、HgはSiO$$_{2}$$表面には吸着せず、Au表面に吸着した。この結果より、本実験のセットアップを用いることで短寿命Hg, Tl, Pb同位体の吸着特性を調べることができると証明され、この手法がCn, Nh, Flの実験にも適用できることが確認された。


Characteristics of TPDN/SiO$$_{2}$$-P adsorbent for MA(III) recovery

小藤 博英; 渡部 創; 竹内 正行; 鈴木 英哉; 松村 達郎; 塩飽 秀啓; 矢板 毅

Progress in Nuclear Science and Technology (Internet), 5, p.61 - 65, 2018/11

Applicability of newly developed MA(III)/RE(III) separation extractant TPDN for the extractionchromatography technology was evaluated through series of fundamental characterizations. The adsorbentselectively extract $$^{241}$$Am from diluted high level liquid waste and sufficient performance for MA(III)/RE(III)separation process was confirmed. Durability and behavior in the vitrification process of the adsorbent alsosuggested that the new adsorbent can be employed as a material for reprocessing of spent fuels.


Microscopic analyses of complexes formed in adsorbent for Mo and Zr separation chromatography

安倍 諒治*; 名越 航平*; 新井 剛*; 渡部 創; 佐野 雄一; 松浦 治明*; 高木 秀彰*; 清水 伸隆*; 江夏 昌志*; 佐藤 隆博*

Nuclear Instruments and Methods in Physics Research B, 404, p.173 - 178, 2017/08

 被引用回数:5 パーセンタイル:47.28(Instruments & Instrumentation)

Molybdenum and zirconium obstruct the efficient recovery of minor actinides (MA(III): Am(III) and Cm(III)) by extraction chromatography; hence, the removal of these elements prior to MA(III) recovery is desirable. The use of an adsorbent impregnated with bis(2-ethylhexyl) hydrogen phosphate (HDEHP) for Mo and Zr decontamination was evaluated in this report. The adsorption/elution and column separation experiments showed that Mo and Zr in the simulated HLLW were selectively adsorbed on the particles, and that Mo was eluted by H$$_{2}$$O$$_{2}$$. EXAFS analysis and SAXS patterns of the adsorbent containing Zr revealed that the Zr-HDEHP complex had a crystal-like periodic structure similar to the structure of the precipitate produced in the solvent extraction system. Micro-PIXE analysis revealed that distribution of the residual Zr on the adsorbent was uniform.


Minor actinides recovery from irradiated fuel for SmART cycle test

竹内 正行; 佐野 雄一; 渡部 創; 中原 将海; 粟飯原 はるか; 小藤 博英; 小泉 務; 水野 朋保

Proceedings of 2017 International Congress on Advances in Nuclear Power Plants (ICAPP 2017) (CD-ROM), 6 Pages, 2017/04

SmART cycle test has been promoted for reduction of volume and radiotoxicity of vitrified waste. It is a fuel cycle test using small amount of minor actinides (MA) in irradiated FBR fuels. The plan includes U, Pu and MA partitioning, fuel fabrication, irradiation at FBR and post irradiation examination. In this paper, a series of radioactive tests for MA partitioning from the irradiated fuel were mainly focused. As treatment of the irradiated fuel, it was sheared and dissolved by hot nitric acid, and then, U, Pu and Np in the dissolved fuel solution are co-extracted by solvent extraction. Am and Cm in the raffinate are efficiently separated by chromatographic technique. The target of MA yield for this cycle test is more than 1g to fabricate MOX pellets bearing 5% MA. As the current status for the MA partitioning, we have successfully finished the shearing and dissolution of the irradiated FBR fuel and solvent extraction process and the two steps flowsheet for Am and Cm partitioning from the raffinate and denitration behavior of separation product solution was discussed.


Flow-sheet study of MA recovery by extraction chromatography for SmART cycle project

渡部 創; 野村 和則; 北脇 慎一; 柴田 淳広; 小藤 博英; 佐野 雄一; 竹内 正行

Procedia Chemistry, 21, p.101 - 108, 2016/12


 被引用回数:11 パーセンタイル:98.74

Optimization in a flow-sheet of the extraction chromatography process for minor actinides (MA(III); Am and Cm) recovery from high level liquid waste (HLLW) were carried out through batch-wise adsorption/elution experiments on diluted HLLW and column separation experiments on genuine HLLW. Separation experiments using CMPO/SiO$$_{2}$$-P and HDEHP/SiO$$_{2}$$-P adsorbent columns with an improved flow-sheet successfully achieved more than 70 % recovery yields of MA(III) with decontamination factors of Ln(III) $$>$$ 10$$^{3}$$, and a modified flow-sheet for less contamination with fission products was proposed consequently. These results will contribute to MA(III) recovery operations for SmART Cycle project in Japan Atomic Energy Agency which is planned to demonstrates FR fuel cycle with more than 1g of Am.


Vacuum chromatography of Tl on SiO$$_{2}$$ at the single-atom level

Steinegger, P.*; 浅井 雅人; Dressler, R.*; Eichler, R.*; 金谷 佑亮*; 水飼 秋菜*; 永目 諭一郎; Piguet, D.*; 佐藤 哲也; Sch$"a$del, M.; et al.

Journal of Physical Chemistry C, 120(13), p.7122 - 7132, 2016/04

 被引用回数:21 パーセンタイル:59.81(Chemistry, Physical)



Particle induced X-ray emission-computed tomography analysis of an adsorbent for extraction chromatography

佐藤 隆博; 横山 彰人; 喜多村 茜; 大久保 猛; 石井 保行; 高畠 容子; 渡部 創; 駒 義和; 加田 渉*

Nuclear Instruments and Methods in Physics Research B, 371, p.419 - 423, 2016/03

 被引用回数:7 パーセンタイル:57.38(Instruments & Instrumentation)

The cross-sectional distribution of neodymium (Nd) simulating minor actinides (MA) in a minute globular adsorbent of less than 50 $$mu$$m in diameter was measured using PIXE (particle induced X-ray emission)-CT (computed tomography) with a 3-MeV proton microbeam for the investigation of residual MA in extraction chromatography of spent fast reactor fuel. The measurement area was 100 $$times$$ 100 $$mu$$m$$^2$$ corresponding to 128 $$times$$ 128 pixels of projection images. The adsorbent target was placed on an automatic rotation stage with 9$$^{circ}$$ step. Forty projections of the adsorbent were finally measured, and image reconstruction was carried out by the modified ML-EM (maximum likelihood expectation maximization) method. As a result, the cross-sectional distribution of Nd in the adsorbent was successfully observed, and it was first revealed that Nd remained in the region corresponding to internal cavities of the adsorbent even after an elution process. This fact implies that the internal structure of the adsorbent must be modified for the improvement of the recovery rate of MA.


Irradiation degradation of adsorbents for minor actinides recovery

渡部 創; 佐野 雄一; 小藤 博英; 竹内 正行; 小泉 務

NEA/NSC/R(2015)2 (Internet), p.338 - 344, 2015/06

Extraction chromatography is one of the promising technologies for minor actinides (MA; Am and Cm) recovery from high level liquid waste. Some types of solid adsorbents with extractants are used for the separation process, and they include consequently some organic species such as extractants to get an excellent separation performance. Therefore, the degradation behavior of the organic species in the adsorbents under radiation exposure is greatly important to discuss the safety and durability of the adsorbent. In this study, $$gamma$$-ray irradiation experiments on TODGA/SiO$$_{2}$$-P adsorbent were carried out to investigate the degradation products from radiolysis of the adsorbent. The degradated organic species eluted from the adsorbent and those remaining inside the adsorbent were thoroughly identified by GC/MS, FT-IR and NMR analyses. Some species which suspected as hydrolysis products of TODGA were mainly detected. Since some radicals such as $$^{cdot}$$H or $$^{cdot}$$OH are generated by the $$gamma$$-ray irradiation on water molecules, it was discussed that the radicals products from radiolysis of HNO$$_{3}$$ solution are related to the degradation reaction the extractants.


Chromatographic separation of nuclear rare metals by highly functional xerogels

大西 貴士; 小山 真一; Masud, R. S.*; 河村 卓哉*; 三村 均*; 新堀 雄一*

日本イオン交換学会誌, 25(4), p.220 - 227, 2014/11

環境負荷低減および資源有効利用を目的として、原子力機構と東北大学では高レベル放射性廃液中に含まれるCs, Pd, TcおよびMoを高純度で回収するための技術開発を実施している。その一環として、新規に合成した吸着剤(高機能性キセロゲル)を用いて、模擬高レベル放射性廃液(コールド試薬を用いて調製した溶液)中に含まれるCs, Pd, Re(Tcの代替元素)およびMoを、カラム法により選択的に分離できることを見出している。一方で、照射済燃料から調製され放射性元素を含む溶液を用いたカラム試験は実施されていない。よって、本研究では、照射済燃料を酸溶解して照射済燃料溶解液を調製し、その中に含まれるCs, Pd, TcおよびMoを、高機能性キセロゲル充填カラムに吸着/溶離させることを試みた。その結果、照射済燃料溶解液中のCs, Pd, TcおよびMoを吸着/溶離させる条件を見出した。さらに、Tcについては選択的に分離することに成功した。


Flow injection extraction chromatography with ICP-MS for thorium and uranium determination in human body fluids

Tolmachyov, S.; 桑原 潤*; 野口 宏

Journal of Radioanalytical and Nuclear Chemistry, 261(1), p.125 - 131, 2004/07

 被引用回数:23 パーセンタイル:80.62(Chemistry, Analytical)

人の体液(尿と血液)中のトリウムとウランを同時に定量するため、ICP-MSと結合したフローインジェクション抽出クロマトグラフィーを用いた方法を開発し、その妥当性を検証した。抽出クロマトグラフィーを用いることによって、$$^{232}$$Th, $$^{235}$$U及び$$^{238}$$Uの検出下限値として、それぞれ0.06, 0.0014及び0.05ng/lを達成した。本方法のaccuracyは$$^{232}$$Thと$$^{238}$$Uに対して、それぞれ、102.4と101.5%であり、全precisionは5.3と4.9%であった。$$^{235}$$U/$$^{238}$$Uの比は1.8%のprecisionで測定できた。この技術をマイクロウェーブ法で灰化した人の尿と血液試料中のトリウムとウランの同時分析に適用し、その妥当性を検証した。



吉田 善行; 木原 壯林*; 藤永 太一郎*

分析化学, 53(4), p.195 - 205, 2004/04

 被引用回数:1 パーセンタイル:1.01(Chemistry, Analytical)



Elemental groups separation for high-level waste partitioning using a novel silica-based CMPO extraction-resin

星 陽崇*; Wei, Y.*; 熊谷 幹郎*; 朝倉 俊英; 内山 軍蔵*

Journal of Nuclear Science and Technology, 39(Suppl.3), p.874 - 877, 2002/11

われわれは、高レベル廃液(HLLW)の管理を容易にし、地層処分時の長期放射線リスクを最小化するために、用いる有機溶媒が最小量で済み、装置がコンパクトな抽出クロマトグラフィーによりHLLWから長半減期のマイナーアクチノイド(MA)やZrやMoのような核分裂生成物(FP)を分離する、高度な元素群分離プロセスを提案してきた。本研究では、マクロレティキュラー型スチレン-ジビニルベンゼン共重合体が直径50$$mu$$mの多孔性シリカ粒子内に固定された担体(SiO$$_{2}$$-P)にCMPO (octyl(phenyl)-N, N-diisobutylcarbamoylmethylphosphine oxide)を担持した新しい抽出樹脂を調整し、トレーサー量の$$^{243}$$Am(III)とマクロ量の典型的なFP元素を含む模擬HLLWを用いて、カラムクロマトグラフィーによる分離実験を行い、その結果、模擬HLLW中の元素を3つの群、すなわちCs-Sr-Rh-Ru群,Pd-Ln-Am群及びZr-Mo群に分離することに成功した。


Determination of $$^{36}$$Cl in biological shield concrete using pyrohydrolysis and liquid scintillation counting

伊藤 光雄; 渡部 和男; 畠山 睦夫; 立花 光夫

Analyst, 127(7), p.964 - 966, 2002/06

 被引用回数:13 パーセンタイル:38.98(Chemistry, Analytical)



Determination of $$^{41}$$Ca in biological-shield concrete by low-energy X-ray spectrometry

伊藤 光雄; 渡部 和男; 畠山 睦夫; 立花 光夫

Analytical and Bioanalytical Chemistry, 372(5-6), p.532 - 536, 2002/03

 被引用回数:16 パーセンタイル:45.07(Biochemical Research Methods)



Application of high-performance gel permeation chromatography to aquatic humic substances in natural waters

長尾 誠也; 妹尾 宗明

Humic Substances and Organic Matter in soil and Water Environments: Characterization,Transformations, 0, p.71 - 79, 1996/00



Determination of chlorine in graphite by combustion-ion chromatography

L.Chan*; 渡部 和男; 伊藤 光雄

JAERI-Research 95-061, 13 Pages, 1995/09




Analysis of highly radioactive liquid samples by ICP-MS

M.Betti*; J.I.G.Alonso*; P.Arbore*; L.Koch*; 佐藤 忠

Applications of Plasma Source Mass Spectrometry II, 8 Pages, 1993/00



Study on life estimation of cable insulation by gas evolution and oxygen consumption during radiation and thermal aging

奥田 智昭*; 金光谷 和彦*; 古川 清志*; 八木 敏明; 瀬口 忠男

Proc. on the Electrical Electronics Insulation Conf. and Electrical Manufacturing & Coil Winding Conf., p.703 - 706, 1993/00


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