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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.


Selective Sc recovery from rare earths in nitric acid medium by extraction chromatography

渡部 創; 鈴木 英哉; 後藤 一郎*; 小藤 博英; 松村 達郎

日本イオン交換学会誌, 29(3), p.71 - 75, 2018/09

Chemical compounds containing scandium (Sc) are widely applied to various fields such as catalysts, alloys, lamps and etc. Sc is found in mineral ore, and it is necessary to develop efficient Sc separation and recovery technology for the industrial applications. So far, solvent extraction based processes were proposed as promising Sc recovery procedures. Our group has found that hexaoctyl nitrilotriacetic acid triamide (HONTA) has strong affinity to Sc. In this study, applicability of the extraction chromatography technology for the selective Sc recovery was experimentally evaluated through batch-wise adsorption/elution studies and column separation experiments.


CFD analysis for U extraction in a centrifugal contactor

佐野 雄一; 坂本 淳志; 小藤 博英; 竹内 正行

Proceedings of 21st Pacific Basin Nuclear Conference (PBNC 2018) (USB Flash Drive), p.314 - 318, 2018/09



Am, Cm recovery from genuine HLLW by extraction chromatography

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

Journal of Radioanalytical and Nuclear Chemistry, 316(3), p.1113 - 1117, 2018/06

 被引用回数:4 パーセンタイル:56.63(Chemistry, Analytical)

Am(III) and Cm(III) recovery experiments with the extraction chromatography technology were carried out on genuine HLLW obtained by reprocessing of the Fast Reactor fuel. Modification of the flow-sheet with 2 steps column operations using CMPO/SiO$$_{2}$$-P and HDEHP/SiO$$_{2}$$-P adsorbents achieved more than 90% recovery yields for Am(III) and Cm(III) with decontamination factor of 1000 for Eu(III). This is a significant progress in development of the technology for the implementation.


Micro-PIXE analysis on adsorbent of extraction chromatography for MA(III) recovery

高畠 容子; 渡部 創; 小藤 博英; 竹内 正行; 野村 和則; 佐藤 隆博*

International Journal of PIXE, 26(3&4), p.73 - 83, 2017/09




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.


Granulation study of porous silica particles for MA recovery process

後藤 一郎; 小藤 博英; 折内 章男; 渡部 創; 竹内 正行

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



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:7 パーセンタイル:98.45

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.


Redox equilibrium of the UO$$_2^{2+}$$/UO$$_2^{+}$$ couple in Li$$_{2}$$MoO$$_{4}$$-Na$$_{2}$$MoO$$_{4}$$ eutectic melt at 550$$^{circ}$$C

永井 崇之; 上原 章寛*; 藤井 俊行*; 佐藤 修彰*; 小藤 博英; 明珍 宗孝; 山名 元*

Journal of Nuclear Materials, 454(1-3), p.159 - 163, 2014/11

 被引用回数:0 パーセンタイル:0.01(Materials Science, Multidisciplinary)

550$$^{circ}$$Cの溶融Li$$_{2}$$MoO$$_{4}$$-Na$$_{2}$$MoO$$_{4}$$共晶塩中のUOUO$$_2^{2+}$$/UOUO$$_2^{+}$$対の酸化還元平衡を、サイクリックボルタンメトリ及び吸光分光測定で評価した。サイクリックボルタンメトリにより、UO$$_2^{2+}$$/UO$$_2^{+}$$対の標準酸化還元電位の概略値を求めた。さらに、UO$$_{2}$$$$^{+}$$を含む浴塩にUO$$_2^{2+}$$含有試料を添加しながら吸光スペクトルと浸漬電位を測定し、スペクトルから評価したUO$$_2^{2+}$$とUOUO$$_2^{+}$$の濃度比と浸漬電位の関係から、UOUO$$_2^{2+}$$/UO$$_2^{+}$$対の標準酸化還元電位-0.847$$pm$$0.010 V vs. O$$_{2}$$/O$$^{2-}$$を求めた。


Optimization of chemical composition in the iron phosphate glass as the matrix of high level waste generated from pyroprocessing

小藤 博英; 矢野 哲司*; 明珍 宗孝; 松山 加苗*; 沖田 壮史*; 宮本 真哉*

Proceedings of 22nd International Conference on Nuclear Engineering (ICONE-22) (DVD-ROM), 6 Pages, 2014/07



Chemical durability of iron-phosphate glass as the high level waste from pyrochemical reprocessing

小藤 博英; 矢野 哲司*; 明珍 宗孝; 松山 加苗*; 沖田 壮史*; 宮本 真哉*

Procedia Chemistry, 7, p.764 - 771, 2012/00

 被引用回数:8 パーセンタイル:93.8



Precipitation behaviors of fission products by phosphate conversion in LiCl-KCl medium

天本 一平; 小藤 博英; 明珍 宗孝; 高崎 康志*; 矢野 哲司*; 寺井 隆幸*

Nuclear Technology, 171(3), p.316 - 324, 2010/09

 被引用回数:11 パーセンタイル:63.66(Nuclear Science & Technology)



Electro-deposition behavior of minor actinides with liquid cadmium cathodes

小藤 博英; 福嶋 峰夫; 北脇 慎一; 明珍 宗孝; Kormilitsyn, M. V.*; 寺井 隆幸*

IOP Conference Series; Materials Science and Engineering, 9, p.012010_1 - 012010_8, 2010/05

 被引用回数:0 パーセンタイル:1.02

Transuranic elements would be electro-deposited simultaneously with liquid cadmium cathode (LCC) and be decontaminated from fission products (FP) dissolved in molten 3LiCl-2KCl in the electrorefining step of the metal electrorefining process. Some lab-scale experiments of electrolysis were carried out with uranium (U), plutonium (Pu) and minor actinides elements (MA) in order to evaluate the performance of LCC. As the results of experiments, it was confirmed that neptunium (Np), americium (Am) and curium (Cm) could be recovered with Pu into LCC by the electrolysis operation. The separation factors of MA vs. Pu were estimated to be about 0.7 to 2.5.


Separation of lanthanoid phoshates from the spent electrolyte of pyroprocessing

天本 一平; 小藤 博英; 明珍 宗孝; 都築 達也*; 高崎 康志*; 矢野 哲司*; 寺井 隆幸*

Proceedings of 12th International Conference on Environmental Remediation and Radioactive Waste Management (ICEM '09/DECOM '09) (CD-ROM), 9 Pages, 2009/10



Phosphate conversion behaviors of FP chlorides with spent electrolyte recycling

小藤 博英; 天本 一平; 佐々木 一哉*; 安本 勝*; 高崎 康志*; 明珍 宗孝; 寺井 隆幸*

電気化学及び工業物理化学, 77(8), p.597 - 600, 2009/08

 被引用回数:0 パーセンタイル:0.01(Electrochemistry)



Phosphates behaviours in conversion of FP chlorides

天本 一平; 小藤 博英; 明珍 宗孝; 高崎 康志*; 寺井 隆幸*

Journal of Nuclear Materials, 389(1), p.142 - 148, 2009/05

 被引用回数:14 パーセンタイル:70.47(Materials Science, Multidisciplinary)



Evaluation of phosphate thermodynamic properties for spent electrolyte recycle

小藤 博英; 天本 一平; 安本 勝*; 佐々木 一哉*; 明珍 宗孝; 寺井 隆幸*

Journal of Nuclear Materials, 389(1), p.173 - 178, 2009/05

 被引用回数:3 パーセンタイル:26.15(Materials Science, Multidisciplinary)



Effect of pulse electrolysis on morphology of co-deposited MOX granules

小藤 博英; 岡村 信生; 水口 浩司*; 明珍 宗孝

Journal of Nuclear Science and Technology, 45(9), p.942 - 950, 2008/09

 被引用回数:1 パーセンタイル:10.92(Nuclear Science & Technology)

酸化物電解法乾式再処理技術のMOX共析工程におけるパルス電解法の適用性を、U, Pu,模擬FP及びCPを用いた実験により評価した。実験により不純物やパルス波形が析出物に与える影響が明らかになった。特に電流を停止している間の析出物の溶解挙動が重要である。結果として、MOX中のPu富化度を向上させる波形が確認され、さらに析出物組成が均質化することが明らかとなった。これらの電解挙動を定性的にモデル化して検討を行った。



天本 一平; 小藤 博英; 明珍 宗孝; 寺井 隆幸*

シミュレーション, 27(3), p.189 - 197, 2008/09



Fundamental study on electrolyte recycle process by phosphate conversion technique

天本 一平; 小藤 博英; 明珍 宗孝; 寺井 隆幸*

Proceedings of International Conference on Advanced Nuclear Fuel Cycles and Systems (Global 2007) (CD-ROM), p.748 - 757, 2007/09


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