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論文

Adsorption mechanism of Eu onto newly synthesized fluorous-compound-impregnating adsorbent

荒井 陽一; 渡部 創; 渡部 雅之; 新井 剛*; 勝木 健太*; 吾郷 友宏*; 藤川 寿治*; 武田 啓佑*; 福元 博基*; 保科 宏行*; et al.

Nuclear Instruments and Methods in Physics Research B, 554, p.165448_1 - 165448_10, 2024/09

 被引用回数:0 パーセンタイル:0.00(Instruments & Instrumentation)

Radioactive aqueous and organic liquid wastes contaminated by U and radioactive materials have been generated through solvent extraction experiments on nuclear fuel materials. Although incineration and denitrification / conversion processes are promising for treatment of such liquid wastes, installation of large equipment is essential. Treatment of liquid wastes generated from the reprocessing experiments is one of important tasks of Systematic Treatments of RAdioactive liquid wastes for Decommissioning (STRAD) project, and the recovery technologies of nuclear materials from the spent solvent has been developed. However, recovery of trace amounts of nuclear fuel material from aqueous solutions with wide pH range is still a challenging task. In our previous study, the porous silica particles with a high specific surface area bearing the iminodiacetic acid (IDA) functional group were revealed to be applicable to recover cations. Although the IDA group introduced adsorbents showed an excellent adsorption reaction from the aqueous solution, further improvement related to the adsorption amount is indispensable for application to the radioactive liquid treatment. In this study, fluorous ligands with IDA group were newly synthesized, and its complexation behavior with cations was investigated in order to understand the adsorption mechanism.

論文

Evaluation of the remaining spent extraction solvent in vermiculite after leaching tests via PIXE analysis

荒井 陽一; 渡部 創; 長谷川 健太; 岡村 信生; 渡部 雅之; 武田 啓佑*; 福元 博基*; 吾郷 友宏*; 羽倉 尚人*; 塚原 剛彦*

Nuclear Instruments and Methods in Physics Research B, 542, p.206 - 213, 2023/09

 被引用回数:1 パーセンタイル:41.04(Instruments & Instrumentation)

Spent PUREX solvent, which mainly consists of tributyl phosphate (TBP) and normal dodecane, is generated by solvent extraction of Plutonium and Uranium in the spent nuclear fuel reprocessing. One of the treatment options for storage of the spent solvent is adsorption of the liquid into vermiculite. The organic liquid is considered to be trapped between layers of the vermiculite. Our previous experiments on the adsorption of spent solvent into the vermiculite have shown that some parts of loaded solvent gradually leaked out from the vermiculite. In order to investigate the adsorption mechanism and capacity, elution behavior of the loaded solvent into organic diluents were evaluated. A part of the loaded solvent was easily leaked into the diluent, while some solvent remained inside the particle even after the leaching test. In this study, the adsorption capacity of the vermiculite was evaluated through amount of remaining solvent after washing with diluents. The amount of the remaining solvent was analyzed by Particle Induced X-ray Emission (PIXE) on P contained in TBP. Peak intensity of P-K$$alpha$$ line depended on the washing condition, and the behavior of the amount of change in adsorbed P atom qualitatively agreed with the results of the leaching test.

論文

Improvement in the elution performance of an N,N,N',N-tetraoctyl diglycolamide impregnated extraction chromatography adsorbent using neodymium via micro-particle-induced X-ray emission analysis

高畠 容子; 渡部 創; 新井 剛*; 佐藤 隆博*; 柴田 淳広

Applied Radiation and Isotopes, 196, p.110783_1 - 110783_5, 2023/06

 被引用回数:1 パーセンタイル:41.04(Chemistry, Inorganic & Nuclear)

An adsorbent used for the recovery of trivalent minor actinides (MA(III); Am and Cm) from high level liquid waste generated from reprocessing of spent nuclear fuel was subjected to micro-PIXE analysis to improve its elution performance. The experimental adsorbent comprised SiO$$_{2}$$ particles, a polymer coating, and an TODGA. The particles to be analyzed were subjected to Nd adsorption and an elution operation, but Nd in the adsorbent was found to be uniformly distributed. This might have been caused by individual differences in the amount of impregnated TODGA. The remaining Nd species were not localized to a specific part of the adsorbent after the adsorption operation. Some Nd elements were retained in the adsorbent after elution, probably because of the poor diffusion of the mobile phase inside the adsorbent. An adsorbent having a different microstructure from the first was then evaluated, and rapid elution was observed on new adsorbent along micro-PIXE analysis

論文

Replication of individual snow crystals for their subsequent chemical analysis using micro-PIXE

笠原 三紀夫*; Ma, C.-J.*; 奥村 智憲*; 小嶋 拓治; 箱田 照幸; 酒井 卓郎; 荒川 和夫

JAERI-Review 2003-033, TIARA Annual Report 2002, p.270 - 272, 2003/11

雪は、その結晶化における不均一核生成過程でエアロゾルとともに大気中の物質を捕捉し移動させる。しかし、いろいろな結晶構造を持つ集合体であるために、このような環境浄化機能を雨滴と直接比較することは困難である。このため、乳化剤を塗布したフィルム上で雪試料を固定化することにより、個々の粒子のレプリカ試料を調製した。そして、原研のマイクロPIXE分析及び京大のPIXE分析により、雪の物質捕捉機能と化学的性質を調べた。この結果、以下のことがわかった。(1)雪結晶粒の大きさ(外周円の直径)は0.12-2.5mmであること,(2)六角形から樹枝状に成長すること,(3)捕捉された元素は主として、Si, S, K, Ca, Fe, Sであること,(4)結晶粒の大きさと捕捉元素質量とには相関関係があること。これらから、雪の単結晶内外の元素の化学的内部構造と混合状態を推定することができた。

報告書

原研・大学プロジェクト共同研究シンポジウム報告書; 放射線高度利用研究の成果と今後の展望,1999年1月27日,国立教育会館,東京

原研・大学プロジェクト共同研究放射線高度利用研究プロジェクト専門部会; 大学・原研プロジェクト共同研究放射線高度利用研究専門委員会

JAERI-Conf 2000-008, 113 Pages, 2000/06

JAERI-Conf-2000-008.pdf:11.5MB

本報告は、平成11年1月27日、東京において開催された「原研・大学プロジェクト共同研究シンポジウム; 放射線高度利用研究の成果と今後の展望」をまとめたものである。これまでも研究成果を発表する機会を設けてきたが、今回のシンポジウムではさらに放射線高度利用研究プロジェクトの将来を議論するという試みを初めて行った。研究発表では、(1)オンライン同位体分離器を用いた核分光・核物性、(2)加速器放射線に関する研究(線源評価及び遮蔽)、(3)イオンビーム利用による材料開発法の研究、(4)高分子材料のイオン照射ミクロ構造に関する研究、(5)核融合炉材料に対する核変換生成物の影響に関する研究、(6)ポジトロン放出核種を用いた植物の生体機能解明、の各研究テーマで最近得られた成果が発表された。新しい研究テーマとして、「大気マイクロPIXE分析システムの開発とその応用」が提案され、8人のパネリストによって、本プロジェクトのこれまでの歩みと将来が議論された。

口頭

Evaluation of remaining spent extraction solvent in vermiculite by PIXE analysis

荒井 陽一; 渡部 創; 長谷川 健太; 岡村 信生; 渡部 雅之; 武田 啓佑*; 福元 博基*; 吾郷 友宏*; 羽倉 尚人*; 塚原 剛彦*

no journal, , 

The spent extraction solvent, which mainly consists of tributyl phosphate (TBP) and normal dodecane, is generated by solvent extraction of Plutonium and Uranium in the reprocessing. The spent solvent should be appropriately treated for disposal or storage. One of the treatment options for storage of the spent solvent is adsorption of the liquid into vermiculite. Our previous experiments on the adsorption of spent solvent into the vermiculite have shown that some parts of loaded solvent gradually leaked out from the vermiculite. In order to investigate the adsorption mechanism and capacity more precisely, elution behavior of loaded solvent into hexane or acetone was evaluated. In this study, the adsorption capacity of the vermiculite was evaluated through amount of remaining solvent after washing with diluents. The amount of the remaining solvent was analyzed by Particle Induced X-ray Emission (PIXE) on P contained in TBP. Peak intensity of P-K$$alpha$$ line depended on the washing condition, and the behavior qualitatively agreed with the results of the leaching test.

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