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論文

Waste management in a Hot Laboratory of Japan Atomic Energy Agency, 2; Condensation and solidification experiments on liquid waste

渡部 創; 小木 浩通*; 柴田 淳広; 野村 和則

International Journal of Nuclear and Quantum Engineering (Internet), 13(4), p.169 - 174, 2019/04

STRADプロジェクトの一環として、RO膜装置を用いた放射性廃液の濃縮試験を実施した。溶液中のアンモニウムイオンが濃縮され、廃液中の濃度を目標値である100ppmより低下させることに成功した。水相及び有機相廃液の固化試験も合わせて実施し、それぞれセメント又は凝固剤を添加することで固化することに成功した。しかし長期保管の観点からは添加材の最適化が必要であることが分かった。

論文

Waste management in a hot laboratory of Japan Atomic Energy Agency, 1; Overview and activities in chemical processing facility

野村 和則; 小木 浩通*; 中原 将海; 渡部 創; 柴田 淳広

International Journal of Nuclear and Quantum Engineering (Internet), 13(5), p.209 - 212, 2019/00

Chemical Processing Facility of Japan Atomic Energy Agency is a basic research field for advanced back-end technology developments with using actual high-level radioactive materials. Most of them were treated properly and stored in the liquid waste vessel, but some were not treated and remained at the experimental space as a kind of legacy nuclear waste, which we must treat in safety and dispose if we continue research activities in the facility. Under this circumstance, we launched a collaborative research project called the STRAD project, which stands for Systematic Treatment of Radioactive liquid waste for Decommissioning, in order to develop the treatment processes for wastes of the nuclear research facility. In this project, decomposition methods of certain chemicals, which have been directly solidified without safety pretreatment but may cause a troublesome phenomenon, is developing and a prospect that it will be able to decompose in the facility by simple method. And solidification of aqueous or organic liquid wastes after the decomposition has been studied by adding cement or coagulants. Furthermore, we treated experimental tools of various materials with making an effort to stabilize and to compact them before the package into the waste container. It is expected to decrease the number of transportation of the solid waste and widen the operation space. The project is expected to contribute beneficial waste management outcome that can be shared world widely.

論文

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

 パーセンタイル:100(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.

論文

Partitioning of plutonium by acid split method with dissolver solution derived from irradiated fast reactor fuel with high concentration of plutonium

中原 将海; 佐野 雄一; 野村 和則; 竹内 正行

Journal of Chemical Engineering of Japan, 51(3), p.237 - 242, 2018/03

 パーセンタイル:100(Engineering, Chemical)

酸分配法における高Pu濃度フィード溶液条件におけるPuの分配挙動を調べるため、向流多段試験を行った。フィード溶液に比べてU/PuプロダクトのPu富荷度を1.51倍に高めることができた。Pu分配工程において、Pu重合体や第三相の生成はみられず、安定して遠心抽出器の運転が行われた。

論文

Effect of flowing water on Sr sorption changes of hydrous sodium titanate

高畠 容子; 柴田 淳広; 野村 和則; 佐藤 努*

Minerals (Internet), 7(12), p.247_1 - 247_13, 2017/12

 被引用回数:1 パーセンタイル:68.74(Mineralogy)

福島第一原子力発電所で発生している放射性汚染水の処理に使用されている含水チタン酸ナトリウム(SrTreat)の使用中におけるSr収着能の変化と変化の原因を明らかにするために検討を実施した。含水チタン酸ナトリウムでは99時間の模擬処理水の通水にて表面構造が変化し、H$$^{+}$$に対する緩衝能やSr収着割合が低下した。そのため、含水チタン酸ナトリウムは使用開始初期に変性が起こり、Sr収着能が低下するため、未使用の含水チタン酸ナトリウムのSr収着能を利用して求めた使用済み含水チタン酸ナトリウムのSr含有量は、実際よりも過大量となると想定された。

論文

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

BB2016-1248.pdf:0.36MB

次世代再処理ガラス固化技術基盤研究で技術開発を行っている吸着ガラスについて、開発の対象とする抽出クロマトグラフィ技術に用いる吸着材の吸着元素分布情報をマイクロPIXE分析により明らかにすることを検討している。本研究では高レベル放射性廃液の模擬液をカラム法にて吸着並びに吸着/溶離した吸着材を用いて、実使用に即した条件下での吸着材の元素分布情報取得に対するマイクロPIXE技術の適用性評価を行った。検討に供した吸着材はCMPO/SiO$$_{2}$$-P吸着材及びHDEHP/SiO$$_{2}$$-P吸着材であり、分析には高崎量子応用研究所のシングルエンド加速器を用いた。分析結果より、カラム内での吸着バンドの形成や溶離後に吸着材に残留する元素の存在を確認できた。これより、マイクロPIXE分析を吸着材性能の定性的な評価に適用することが期待できた。

論文

Research of process to treat the radioactive liquid waste containing chloride ion generated by pyroprocessing plant in operating

多田 康平; 北脇 慎一; 渡部 創; 粟飯原 はるか; 柴田 淳広; 野村 和則

Proceedings of International Nuclear Fuel Cycle Conference (GLOBAL 2017) (USB Flash Drive), 3 Pages, 2017/09

塩化物イオン(Cl)を含む放射性廃液は、乾式再処理のプロセス制御における化学分析によって生成される。この廃液を海洋に排出するためには、Clを分離してU, Puを回収する必要がある。本研究では、AgCl沈殿法と抽出クロマトグラフィー法を組み合わせてClを分離し、U, Puを回収した。沈殿試験の結果、UおよびPuが試験後に共沈しないことが分かった。固相抽出試験の結果、95%のPuが液体廃棄物から回収されたことがわかった。Uの濃度が十分でないため、Uについての$$alpha$$放射能を分析することは困難であった。これらの結果は、これらのプロセスが廃液を海に排出する可能性を有することを示した。

論文

Control of fine particles accumulation in the extraction chromatography column system for minor actinide recovery

渡部 創; 後藤 一郎; 佐野 雄一; 野村 和則; 駒 義和

Proceedings of 2017 International Congress on Advances in Nuclear Power Plants (ICAPP 2017) (CD-ROM), 7 Pages, 2017/04

Clogging of the extraction chromatography column caused by inflow of insoluble residue into the bed possible to lead accumulation of decay heat and explosive gas inside the bed. Behavior of small particle is necessary to be investigated to prevent hazardous events. In this study, influence of fine particles contained in the feed solution on the clogging and on separation performance of the bed were evaluated by laboratory scale experiments. Discharging operation of the simulated particles from the bed was experimentally demonstrated using an engineering scale system. The particles were accumulated on top of the bed and hardly come inside the bed. Backwashing operation was effective to discharge a part of the accumulated powder. Supplying water into the column with normal flow rate condition was possible after the short time backwashing operation. Backwashing with cold water as a normal operation must be one of the most appropriate countermeasures for preventing from the clogging.

報告書

東京電力福島第一原子力発電所において採取された汚染水および瓦礫等の分析データ集

浅見 誠*; 高畠 容子; 明道 栄人; 飛田 剛志; 小林 究; 早川 美彩; 薄井 由香; 綿引 博美; 柴田 淳広; 野村 和則; et al.

JAEA-Data/Code 2017-001, 78 Pages, 2017/03

JAEA-Data-Code-2017-001.pdf:4.92MB
JAEA-Data-Code-2017-001-appendix(DVD-ROM).zip:818.06MB

東京電力ホールディングス(東京電力)福島第一原子力発電所において採取された汚染水(滞留水, 処理水)、汚染水処理二次廃棄物、瓦礫、土壌が分析され、放射性核種濃度等の分析データが報告されている。そこで、東京電力, 日本原子力研究開発機構, 国際廃炉研究開発機構により2016年3月末までに公開されたデータを収集し、データ集としてとりまとめた。また分析試料についての情報、分析により得られた放射性核種濃度等の値を表としてまとめるとともに、主な放射性核種濃度の時間変化を表す図を作成して収録した。電子情報として英訳と収録した分析データを提供する。

論文

Characterization of the insoluble sludge from the dissolution of irradiated fast breeder reactor fuel

粟飯原 はるか; 荒井 陽一; 柴田 淳広; 野村 和則; 竹内 正行

Procedia Chemistry, 21, p.279 - 284, 2016/12

BB2015-3214.pdf:0.31MB

 被引用回数:1 パーセンタイル:20.72

Insoluble sludge is generated in reprocessing process. Actual sludge data, which had been obtained from the dissolution experiments of irradiated fuel of fast reactor "Joyo" were reevaluated especially from the view point of the characterization of sludge. The yields of sludge were calculated from the weight and there were less than 1%. Element concentrations of sludge were analyzed after decomposing by alkaline fusion. As the results, molybdenum, technetium, ruthenium, rhodium and palladium accounted for mostly of the sludge. From their chemical compositions and structure analyzed by XRD show good agree that main component of sludge is Mo$$_{4}$$Ru$$_{4}$$RhPdTc regardless of the experimental condition. At the condition of reprocessing fast breeder fuel, it is indicated that molybdenum and zirconium in dissolved solution is low, therefore zirconium molybdate hydrate may not produce abundant amount in the process.

論文

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

BB2015-3215.pdf:0.34MB

 被引用回数:2 パーセンタイル:7.84

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.

論文

Safety operation of chromatography column system with discharging hydrogen radiolytically generated

渡部 創; 佐野 雄一; 野村 和則; 駒 義和; 岡本 芳浩

European Physical Journal; Nuclear Sciences & Technologies (Internet), 1, p.9_1 - 9_8, 2015/12

In the extraction chromatography system, accumulation of hydrogen gas in the chromatography column is suspected to lead to fire or explosion. In order to prevent the hazardous accidents, it is necessary to evaluate behaviors of gas radiolytically generated inside the column. In this study, behaviors of gas inside the extraction chromatography column were investigated through experiments and Computation Fluid Dynamics (CFD) simulation. N$$_{2}$$ gas once accumulated as bubbles in the packed bed was hardly discharged by the flow of mobile phase. However, the CFD simulation and X-ray imaging on $$gamma$$-ray irradiated column revealed that during operation the hydrogen gas generated in the column was dissolved into the mobile phase without accumulation and discharged.

論文

Influence of contaminants from spent fuel pools at the Fukushima Daiichi Nuclear Power Station on the reprocessing process

粟飯原 はるか; 北脇 慎一; 野村 和則; 田口 克也

Proceedings of 21st International Conference & Exhibition; Nuclear Fuel Cycle for a Low-Carbon Future (GLOBAL 2015) (USB Flash Drive), p.1076 - 1083, 2015/09

The water in the spent fuel pools at TEPCO Fukushima Daiichi Nuclear Power Station contains sea water and rubbles. When the spent fuels stored in the pools will be reprocessed, it has possibility that these contaminants enter the reprocessing process with the spent fuels. Therefore it is meaningful to estimate the influence of contaminants on reprocessing process in advance. The purpose of this study is to evaluate the behavior and influence of contaminants on the extraction process of spent fuel reprocessing by using simulated contaminants. Contaminants were dissolved into the heated nitric acid and solvent extraction using TBP was performed to obtain distribution ratios. The estimated amount of contaminants accompanied with the spent fuel is low values and solvent extraction tests showed that the distribution ratios of every major element were very low in any case. Also to evaluate the influence of sulfate and chloride ions on uranium and plutonium extraction, Ce(IV) was used for simulated Pu to predict extraction behavior. And then U and Pu test was conducted in order to confirm the simulated test result. Obtained distribution ratio suggests that contaminants will not affect the extraction process.

論文

Comparative study of Sr adsorbents for radioactive contaminated water on severe accident

高畠 容子; 柴田 淳広; 野村 和則

Proceedings of 21st International Conference & Exhibition; Nuclear Fuel Cycle for a Low-Carbon Future (GLOBAL 2015) (USB Flash Drive), p.2099 - 2104, 2015/09

The radioactive contaminated water has accumulated at Fukushima Dai-ichi Nuclear Power Station after the severe damage by the events accompanying the earthquake and tsunami. The concentration of Ca in the accumulated water is higher than that of Sr. Because of their chemical similarity, the secondary radioactive waste from Sr decontamination process will contains Ca more than Sr. Therefore, the volume of the secondary waste will increase more unnecessarily. Three kinds of Sr adsorbents; SW-KAZLS, the Hydrous titanic acid and SrTreat,were characterized and assessed from the viewpoint of Sr decontamination for radioactive contaminated water. The amount of Sr in SW-KAZLS showed the highest Sr selectivity. Since the Hydrous titanic acid was the hardest adsorbent of three, it is applied well to adsorption tower. The amount of Sr in SrTreat was favorable, and it could be applied to decontamination for the radioactive contaminated water of low Sr concentration.

論文

Safety operation of chromatography column system with discharging hydrogen radiolytically generated

渡部 創; 佐野 雄一; 野村 和則; 駒 義和; 岡本 芳浩

Proceedings of 2015 International Congress on Advances in Nuclear Power Plants (ICAPP 2015) (CD-ROM), p.2781 - 2788, 2015/05

In the extraction chromatography system, accumulation of hydrogen gas in the chromatography column is suspected to lead the fire or explosion. In order to prevent the hazardous accidents, it is necessary to evaluate behaviors of gas radiolytically generated inside the column. In this study, behaviors of gas inside the extraction chromatography column were investigated through experiments and Computation Fluid Dynamics (CFD) simulation. N$$_{2}$$ gas once accumulated as bubbles in the packed bed was hardly discharged by the flow of mobile phase. However, the CFD simulation and X-ray imaging on $$gamma$$-ray irradiated column revealed that during operation the hydrogen gas generated in the column was dissolved into the mobile phase without accumulation and discharged.

論文

Effect of crystal size on purity of uranyl nitrate hexahydrate crystalline particles grown in nitric acid medium

中原 将海; 野村 和則

Radiochimica Acta, 100(11), p.821 - 826, 2012/11

 パーセンタイル:100(Chemistry, Inorganic & Nuclear)

照射済燃料溶解液から回収した硝酸ウラニル六水和物の結晶粒径と除染係数の関係を調べた。表面に付着している液体不純物は、粒径が大きくなると結晶の表面積が小さくなるため、除染係数が高い傾向を示した。しかしながら、固体不純物はそれほど効果がみられなかった。

報告書

照射済高速中性子炉燃料からのセシウムの水及び希薄硝酸溶液に対する溶出特性

中原 将海; 鍛治 直也; 野村 和則

JAEA-Research 2012-009, 15 Pages, 2012/06

JAEA-Research-2012-009.pdf:6.37MB

晶析工程に関してPuとCsの化合物の生成抑制の観点から、原料液中のCsを減少させることが求められている。照射済核燃料中のCsを粗分離するため、純水及び希薄HNO$$_{3}$$における浸漬試験を行った。浸漬67時間後の純水及び0.1mol/dm$$^{3}$$ HNO$$_{3}$$における燃料粉末からのCsの溶出率は、それぞれ33.8及び38.3%であった。燃料溶解前に燃料粉末を純水もしくは希薄HNO$$_{3}$$溶液に浸漬させることによりCsを粗分離できる可能性を示した。

論文

Decontamination of radioactive liquid waste with hexacyanoferrate(II)

高畠 容子; 渡部 創; 柴田 淳広; 野村 和則; 駒 義和

Procedia Chemistry, 7, p.610 - 615, 2012/00

 被引用回数:6 パーセンタイル:6.31

Concerning decontamination of a radioactive liquid waste which comprise seawater and nuclides from irradiated fuels and activated materials, the in-situ generation of metal hexacyanoferrates(II) by adding potassium hexacyanoferrate(II) and co-decontamination of $$^{134,137}$$Cs and some activation products were investigated. Transition metals arising from seawater in the waste solution precipitates in the preference order of Zn $$>$$ Ni $$>$$ Co $$>$$ Mn according to their solubility. The precipitate adsorbs $$^{134,137}$$Cs, and decontamination will be attained by the following sedimentation with a polymer and filtration, as an example. Decontamination factor of activated products, $$^{60}$$Co and $$^{54}$$Mn, is dependent on concentration of hexacyanoferrate(II) in the solution.

論文

Optimizing composition of TODGA/SiO$$_{2}$$-P adsorbent for extraction chromatography process

渡部 創; 新井 剛*; 小川 剛*; 瀧澤 真*; 佐野 恭平*; 野村 和則; 駒 義和

Procedia Chemistry, 7, p.411 - 417, 2012/00

 被引用回数:5 パーセンタイル:7.57

As a part of developing extraction chromatography technology for minor actinides (MA(III); Am and Cm) recovery from spent fast reactor fuels, improvement on the TODGA/SiO$$_{2}$$-P adsorbent to enhance its desorption efficiency was carried out. Batchwise adsorption/elution experiments revealed that 20wt% of the adsorbent concentration impregnated and 10% of cross linkage of polymer gave better desorption ratio than the reference adsorbent. Inactive column separation experiments with the simulated high level liquid waste and the optimized adsorbent revealed that decontamination factors of fission products can also be improved as well as the recovery yields.

論文

Americium and curium separation from simulated acidic raffinate from the reprocessing process by extraction chromatography

松村 達郎; 森田 泰治; 松村 和美; 佐野 雄一; 駒 義和; 野村 和則

Proceedings of 11th OECD/NEA Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation (Internet), 8 Pages, 2012/00

FaCTの一環として、抽出クロマトグラフ法によるMA回収技術を確立するため、担体であるSiO$$_{2}$$-P粒子に抽出剤を担持させた吸着材を用いるフローシートを検討している。抽出クロマトグラフ法においても、抽出剤は溶媒抽出法と同様な特性を発揮すると考えられるため、MA・Ln回収工程とMA/Ln分離工程の2サイクルから構成されるフローシートとして進めている。本研究では、MA・Ln回収工程にTODGA吸着材及びCMPO吸着剤、MA/Ln分離工程にHDEHP吸着材,R-BTP吸着剤及びTOPEN吸着剤を使用した。フローシート全体を通じた各元素の分離挙動を観察した結果、TODGA吸着剤とR-BTP吸着剤あるいはTOPEN吸着剤を組合せたフローシートによってMA(III)を模擬再処理抽残液から分離することが可能であることを確認した。

179 件中 1件目~20件目を表示