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A Phoswich alpha/beta detector for monitoring in the site of Fukushima Daiichi Nuclear Power Station

森下 祐樹; 高崎 浩司; 北山 佳治; 田川 明広; 柴田 卓弥; 星 勝也; 金子 純一*; 樋口 幹雄*; 大浦 正利*

Radiation Measurements, 160, p.106896_1 - 106896_10, 2023/01

 被引用回数:0 パーセンタイル:0.02(Nuclear Science & Technology)



Development of a laser-driven ultrasonic technology for characterizations of heated and aged concrete samples

山田 知典; 大道 博行*; 柴田 卓弥

Journal of Nuclear Science and Technology, 59(5), p.614 - 628, 2022/05

 被引用回数:1 パーセンタイル:20.56(Nuclear Science & Technology)

We have demonstrated a full noncontact laser technology to measure the velocity of ultrasonic waves and their spectra propagated through concrete samples exposed to specified high-temperature conditions with specified durations as models of concrete structures in a severe accident at the Fukushima Daiichi Nuclear Power Station. The velocities and spectra of the ultrasonic waves were strongly dependent on the exposed temperature, i.e., at a high-temperature condition of 400$$^{circ}$$C, the velocity was 3700 m/s, and at room temperature, the velocity was 5000 m/s. Experimental results are almost comparable to those obtained by the contact ultrasonic technique.


Ten years of Fukushima Dai-ichi post-accident research on the degradation phenomenology of the BWR core components

Pshenichnikov, A.; 柴田 裕樹; 山下 拓哉; 永江 勇二; 倉田 正輝

Journal of Nuclear Science and Technology, 59(3), p.267 - 291, 2022/03

 被引用回数:1 パーセンタイル:20.56(Nuclear Science & Technology)

The paper reviews the results of the JAEA and some International activities over the last ten years of research on the understanding of the core components melting and debris formation in boiling water reactors.


Generation of particles and fragments by quasicontinuous wave fiber laser irradiation of stainless steel, alumina, and concrete materials

大道 博行*; 山田 知典; 古河 裕之*; 伊藤 主税; 宮部 昌文; 柴田 卓弥; 長谷川 秀一*

Journal of Laser Applications, 33(1), p.012001_1 -  012001_16, 2021/02

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

In order to preserve a safe working environment, in particular for nuclear decommissioning like the Fukushima Daiichi Nuclear Power Station, special care should be taken to confine and retrieve such particles during laser processing. In the experiments, particle production from the vapor, as well as the molten phase layer in the targeted material were observed with a high speed camera with fine particles collected and analyzed using an electron microscope. The observed results were qualitatively interpreted with the help of a simplified one-dimensional hydrodynamic code coupled with a stress computation code. Characterization and classification of the results are expected to provide a useful database which will contribute to the decommissioning of nuclear facilities as well as other industrial applications.


Non-invasive imaging of radiocesium dynamics in a living animal using a positron-emitting $$^{127}$$Cs tracer

鈴井 伸郎*; 柴田 卓弥; 尹 永根*; 船木 善仁*; 栗田 圭輔; 保科 宏行*; 山口 充孝*; 藤巻 秀*; 瀬古 典明*; 渡部 浩司*; et al.

Scientific Reports (Internet), 10, p.16155_1 - 16155_9, 2020/10

 被引用回数:2 パーセンタイル:27.76(Multidisciplinary Sciences)

Visualizing the dynamics of cesium (Cs) is desirable to understand the impact of radiocesium when accidentally ingested or inhaled by humans. The positron-emitting nuclide $$^{127}$$Cs was produced using the $$^{127}$$I ($$alpha$$, 4n) $$^{127}$$Cs reaction, which was induced by irradiation of sodium iodide with a $$^{4}$$He$$^{2+}$$ beam from a cyclotron. We excluded sodium ions by using a material that specifically adsorbs Cs as a purification column and successfully eluted $$^{127}$$Cs by flowing a solution of ammonium sulfate into the column. We injected the purified $$^{127}$$Cs tracer solution into living rats and the dynamics of Cs were visualized using positron emission tomography; the distributional images showed the same tendency as the results of previous studies using disruptive methods. Thus, this method is useful for the non-invasive investigation of radiocesium in a living animal.


Development of a laser chipping technique combined with water jet for retrieval of fuel debris at Fukushima Daiichi Nuclear Power Station

山田 知典; 武部 俊彦*; 石塚 一平*; 大道 博行*; 羽成 敏秀; 柴田 卓弥; 大森 信哉*; 黒澤 孝一*; 佐々木 豪*; 中田 正宏*; et al.

Journal of Nuclear Science and Technology, 56(12), p.1171 - 1179, 2019/12

 被引用回数:1 パーセンタイル:12.21(Nuclear Science & Technology)



Thermal behavior, structure, dynamic properties of aqueous glycine solutions confined in mesoporous silica MCM-41 investigated by X-ray diffraction and quasi-elastic neutron scattering

吉田 亨次*; 井上 拓也*; 鳥越 基克*; 山田 武*; 柴田 薫; 山口 敏男*

Journal of Chemical Physics, 149(12), p.124502_1 - 124502_10, 2018/09

 被引用回数:3 パーセンタイル:13.67(Chemistry, Physical)

異なる幾つかの、グリシン濃度, pH、および充填率(=グリシン溶液の質量/MCM-41の乾燥質量))をパラメーターとして、メソポーラスシリカ(MCM-41)に閉じ込められたグリシン水溶液の示差走査熱量測定、X線回折および準弾性中性子散乱(QENS)を305-180Kの温度範囲で実施して、グリシン水溶液の熱的挙動, 構造、および動的特性に対する閉じ込め効果を検討した。


Development of a water purifier for radioactive cesium removal from contaminated natural water by radiation-induced graft polymerization

瀬古 典明*; 保科 宏行*; 笠井 昇*; 柴田 卓弥; 佐伯 誠一*; 植木 悠二*

Radiation Physics and Chemistry, 143, p.33 - 37, 2018/02

 被引用回数:15 パーセンタイル:85.6(Chemistry, Physical)

Six years after the Fukushima-nuclear accident, the dissolved radioactive cesium (Cs) is now hardly detected inenvironmental natural waters. These natural waters are directly used as source of drinking and domestic waters in disaster-stricken areas in Fukushima. However, the possibility that some radioactive Cs adsorbed on soil or leaves will contaminate these natural waters during heavy rains or typhoon is always present. In order for the returning residents to live with peace of mind, it is important to demonstrate the safety of the domestic waters that they will use for their daily life. For this purpose, we have synthesized a material for selective removal of radioactive Cs by introducing ammonium 12-molybdophosphate (AMP) onto polyethylene nonwoven fabric through radiation-induced emulsion graft polymerization technique. Water purifiers filled with the grafted Csadsorbent were installed in selected houses in Fukushima. The capability of the grafted adsorbent to remove Cs from domestic waters was evaluated for a whole year. The results showed that the tap water filtered through the developed water purifier contained no radioactive Cs, signifying the very effective adsorption performance of thedeveloped grafted adsorbent. From several demonstrations, we have commercialized the water purifier named "KranCsair".


Neutron irradiation effect of high-density MoO$$_{3}$$ pellets for Mo-99 production, 3

石田 卓也; 鈴木 善貴; 西方 香緒里; 米川 実; 加藤 佳明; 柴田 晃; 木村 明博; 松井 義典; 土谷 邦彦; 佐野 忠史*; et al.

KURRI Progress Report 2015, P. 64, 2016/08



Evaluation of a cesium adsorbent grafted with ammonium 12-molybdophosphate

柴田 卓弥; 瀬古 典明; 天田 春代; 笠井 昇; 佐伯 誠一; 保科 宏行; 植木 悠二

Radiation Physics and Chemistry, 119, p.247 - 252, 2016/02

 被引用回数:11 パーセンタイル:73.32(Chemistry, Physical)

A fibrous adsorbent for radioactive cesium (Cs) removal has been developed by radiation induced graft polymerization. To apply the developed adsorbent to drinking water, the stability of adsorbent having high affinity for Cs ligand, ammonium 12-molybdophosphate (AMP), was evaluated. As a result, since a crosslinking structure was introduced onto the grafted AMP, it could be successfully satisfied the regulation of Food Sanitation Act. Finally, the Cs adsorbent was commercialized as water purifier named by "KranCsairtextregistered".



鈴木 祐未*; 中野 寛子; 鈴木 善貴; 石田 卓也; 柴田 晃; 加藤 佳明; 川又 一夫; 土谷 邦彦

JAEA-Technology 2015-031, 58 Pages, 2015/11


テクネチウム99m($$^{99m}$$Tc)は、核医学分野で一般的に使用される放射性同位元素である。日本原子力研究開発機構では、材料試験炉(Japan Material Testing Reactor: JMTR)を用いた放射化法((n,$$gamma$$)法)によるモリブデン-99($$^{99}$$Mo)製造に関する開発研究が行われている。一方、2013年10月に「核医学検査薬(テクネチウム製剤)の国産化」として新規プロジェクトがつくば国際戦略総合特区に採択され、JMTRを用いた$$^{99}$$Mo/$$^{99m}$$Tc国産化のための実証試験が計画されている。このため、本プロジェクトの一環として、2014年に新しい設備や分析装置をJMTRホットラボ施設内に整備した。本プロジェクトにおける分析装置整備の一環として、$$^{99}$$Mo/$$^{99m}$$Tc溶液及びその溶液から抽出される$$^{99m}$$Tc溶液等の品質検査のために$$gamma$$-TLCアナライザー及びHPLC用放射線検出器が導入された。これらの分析装置は、$$^{99}$$Mo/$$^{99m}$$Tcの代替核種として$$^{137}$$Cs, $$^{152}$$Euを用いて検出感度, 分解能, 直線性, エネルギー範囲の選択性などの性能確認試験を行った。この結果、これらの分析装置を用いることにより、溶液の品質検査の見通しを得た。本報告書は、それらの性能確認試験結果をまとめたものである。



石田 卓也; 椎名 孝行*; 太田 朗生*; 木村 明博; 西方 香緒里; 柴田 晃; 棚瀬 正和*; 小林 正明*; 佐野 忠史*; 藤原 靖幸*; et al.

JAEA-Technology 2015-030, 42 Pages, 2015/11





瀬古 典明; 柴田 卓弥; 笠井 昇; 植木 悠二; 佐伯 誠一; 保科 宏行

放射線と産業, (138), p.9 - 12, 2015/06

福島の原子力発電所災害以降、環境資源材料研究グループでは環境中の水域に飛散した放射性物質のうち、特にセシウムに対して効果のある捕集材料の開発を進めてきた。これまでの実績から水に対して接触効率が良好で、取り扱いの簡便な不織布繊維を基材に用い、これにセシウムに対して親和性のある吸着基を量子ビーム技術を活用した放射線グラフト重合技術により導入した。材料の評価では、福島被災地の各所で実施したフィールドテストで評価を重ね、最終的には井戸水, 沢水を対象にした飲用水向けのモニター試験を進め、その良好な結果から給水器の発売に繋げた経緯について紹介する。


Evaluation of antibacterial effect by using a fibrous grafted material loaded Ag ligand

柴田 卓弥; 瀬古 典明; 笠井 昇; 保科 宏行; 植木 悠二

International Journal of Organic Chemistry, 5(2), p.100 - 107, 2015/06

To obtain the safety of drinking water, an antibacterial material was prepared by loading Ag onto fibrous iminodiacetate (IDA) adsorbent, which was synthesized by radiation induced graft polymerization of a glycidyl methacrylate and subsequent chemical modification of the produced epoxy group to an IDA group(IDA-Ag). A total amount of loaded Ag on the IDA-Ag fabric was 0.4 mmol-Ag/g-fabric. As a result of evaluating antibacterial effects by the column mode water flow test with a stream water, the effective Ag concentration was monitored 0.05 ppm at irrespective of flow rate which was functioned to the antibacterial performance. The antibacterial effects for general bacteria were indicated until BV (BV: steam water volume/IDA-Ag fabric volume) 6,000, and for colitis germ legions were completely disinfected until BV 6,000.


Development of an adsorbent for Cs removal synthesized by radiation-induced graft polymerization

柴田 卓弥; 瀬古 典明; 天田 春代; 笠井 昇; 佐伯 誠一; 保科 宏行; 植木 悠二

日本イオン交換学会誌, 26(1), p.9 - 14, 2015/01

It is important task for recovering of Cs from the contaminated area caused by the accident at the Fukushima Daiichi Nuclear Power Station. We developed a highly efficient Cs adsorbent by radiation grafting of ammonium 12-molybdophosphate (AMP) and crosslinking of grafted chains with a suitable crosslinker at the same time. As a result of the optimizaion, the Cs adsorbent with 1 mol% of polyethylene glycol dimethacrylate satisfied the specification as a water purifier. The resultant grafted Cs adsorbent could work to maintain the highly performance of Cs removal in the standard pH range for drinking water (from pH 5.8 to 8.6) and even in the presence of coexisting ions such as K, Ca, Mg, and Na.


The Volume reduction method of radioactively-contaminated plant waste through extraction and removal of radioactive cesium

佐伯 誠一; 柴田 卓弥; 保科 宏行; 植木 悠二; 笠井 昇; 瀬古 典明

日本イオン交換学会誌, 25(4), p.170 - 175, 2014/11

After Fukushima Daiichi Nuclear Power Plant accidents, a lot of contaminated wastes have been produced by decontamination works at contaminated areas around Fukushima prefecture, Japan. At some temporary storage sites, it was found that contaminated leaching water was accumulated under stacks of contaminated "plant" wastes. To handle the wastes and the solution properly, decontamination tests of the leaching water were examined with molybdophosphate type cesium adsorbents synthesized by radiation-induced grafting method. At batch adsorption tests, 75% of radioactive cesium was successfully removed with cesium adsorbents. At column adsorption tests, radioactivity concentration of the leaching water could be reduced under provisional limit value up to around 500 times volume as large as an adsorbent volume. For development of volume reduction method of contaminated plant wastes, radioactive cesium extraction tests from the wastes and removal tests from the extracts were executed using contaminated oil cakes of sunflower seeds as a model of contaminated plant wastes. As a result, 65% of radioactive cesium was successfully extracted from the oil cakes to liquid phase, and more than 65% of radioactive cesium could be collected from the extract by grafted cesium adsorbents. These results showed a possibility of an application of these processes to volume reduction method for contaminated plant wastes.


Optimization of grafted fibrous polymer as a solid basic catalyst for biodiesel fuel production

植木 悠二; 佐伯 誠一; 柴田 卓弥; 保科 宏行; 笠井 昇; 瀬古 典明

International Journal of Organic Chemistry, 4(2), p.91 - 105, 2014/06



Transmission properties of C$$_{60}$$ ions through micro- and nano-capillaries

土田 秀次*; 間嶋 拓也*; 冨田 成夫*; 笹 公和*; 鳴海 一雅; 齋藤 勇一; 千葉 敦也; 山田 圭介; 平田 浩一*; 柴田 裕実*; et al.

Nuclear Instruments and Methods in Physics Research B, 315, p.336 - 340, 2013/11

 被引用回数:3 パーセンタイル:27.3(Instruments & Instrumentation)

Applying the beam-focusing method with capillaries to C$$_{60}$$ projectiles in the velocity range between 0.14 and 0.2 a.u., transmission properties of C$$_{60}$$ ions through two different types of capillaries are studied: (1) a borosilicate-glass single microcapillary with an outlet diameter of 5.5 $$mu$$m, and (2) an Al$$_{2}$$O$$_{3}$$ multicapillary foil with approximatey 70-nm pores in diameter and a high aspect ratio of approximately 750. Transmitted-particle compositions are measured with the electrostatic-deflection method combined with a two-dimensional position-sensitive detector. In the experiments with the single microcapillary, the main transmitted component is found to be primary C$$_{60}$$ ions, which are focused in the area equal to the capillary outlet diameter. The other components are charge-exchanged C$$_{60}$$ ions and charged or neutral fragments (fullerene-like C$$_{60-2m}$$ and small C$$_{n}$$ particles), and their fractions decrease with decreasing projectile velocity. Similar results are obtained in the experiments with the multicapillary foil. It is concluded from the relative transimission fractions of more than 80% that the C$$_{60}$$ transmission fraction is considerably high for both types of the capillaries in the present velocity range.



見上 隆志*; 中野 正憲*; 柴田 卓弥; 瀬古 典明

設備と管理, 47(4), p.95 - 99, 2013/04



Synthesis of arsenic graft adsorbents in pilot scale

保科 宏行; 笠井 昇; 柴田 卓弥*; 明田川 康*; 高橋 牧克*; 吉井 明央*; 角田 安彦*; 瀬古 典明

Radiation Physics and Chemistry, 81(8), p.1033 - 1035, 2012/08

 被引用回数:4 パーセンタイル:32.65(Chemistry, Physical)

The zirconium (Zr(IV))-type adsorbent for As(V) removal was synthesized by radiation-induced graft polymerization with phosphoric monomer and the subsequent chemical modification with Zr(IV) by loading on phosphoric units. The Zr(IV)-type adsorbent can rapidly remove As(V) to low concentration. In order to apply for a large amount of water treatment, it is necessary to construct of synthesis method in pilot scale. Synthesis method of graft adsorbent in pilot scale was investigated by setting up the equipment which was composed of reaction tanks, washing tank and pump. The equipment can produce the adsorbent which is maximum 0.3 $$times$$ 20 m size in one batch graft reaction. To evaluate the optimum condition in this equipment, it was required the optimization of several condition such absorbed dose, monomer concentration, reaction temperature and reaction time. A nonwoven cotton fabric as a trunk polymer was irradiated, then it was placed into the reaction tank with the deaerated monomer solution. The components of the monomer was phosphoric acid mono- (50%) and di- (50%) ethyl methacrylate ester. As a result, the degree of grafting of 150% was obtained at absorbed dose of 20 kGy with 5% monomer solution mixed by deionized water for 2 hours at 40 $$^{circ}$$C. Finally after loaded of Zr(IV) on grafted nonwoven fabric, As(V) adsorbent was achieved in pilot scale.

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