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Spinmotive force in the out-of-plane direction generated by spin wave excitations in an exchange-coupled bilayer element

Zhou, W.*; 関 剛斎*; 今村 裕志*; 家田 淳一; 高梨 弘毅*

Physical Review B, 100(9), p.094424_1 - 094424_5, 2019/09

 被引用回数:0 パーセンタイル:100(Materials Science, Multidisciplinary)

The generation of the spinmotive force (SMF) requires the temporal and spatial variations of the magnetic moments. We explore an approach to satisfy this requirement by creating asymmetry in a thin film structure along the out-of-plane direction, through the use of an exchange-coupled $$L$$1$$_{0}$$-FePt / Ni$$_{81}$$Fe$$_{19}$$ bilayer element. As the spin wave is excited by rf magnetic field, a continuous dc voltage signal along the out-of-plane direction of the bilayer element appears. The sign of the voltage signal and its microwave power dependency agree with the theoretical framework of the SMF. The corresponding spin wave modes are revealed by carrying out the micromagnetic simulation. Our results demonstrate the generation of the SMF using a vertically structured element in addition to previously reported in-plane structured devices.



長尾 郁弥; 新里 忠史; 佐々木 祥人; 伊藤 聡美; 渡辺 貴善; 土肥 輝美; 中西 貴宏; 佐久間 一幸; 萩原 大樹; 舟木 泰智; et al.

JAEA-Research 2019-002, 235 Pages, 2019/08




Research on activation assessment of a reactor structural materials for decommissioning

関 美沙紀; 石川 幸治*; 永田 寛; 大塚 薫; 大森 崇純; 花川 裕規; 井手 広史; 土谷 邦彦; 佐野 忠史*; 藤原 靖幸*; et al.

KURNS Progress Report 2018, P. 257, 2019/08

JMTR施設の廃止措置を進めるにあたり、多くの放射性廃棄物が発生するが、これらはドラム缶等に格納し、コンクリートを充填して、廃棄体とする計画である。しかし、アルミニウムは、コンクリートと反応し水素ガスが発生し、廃棄体を破損することが懸念されている。本研究は、湿式法によるアルミニウムの安定化処理法の開発を行った。JMTRで多く使用されている2種類のアルミニウム試料を準備し、KURで照射した後、強塩基であるNaOHに溶解した。溶解液をろ過した後、中和処理をしてAl(OH)$$_{3}$$を生成した。それぞれの工程で得た残差及び溶液は、放射化分析を行った。この結果、Al合金内に含まれる不純物$$^{51}$$Crおよび$$^{59}$$FeはAl成分と分離することができ、低レベルのAl(OH) $$_{3}$$の抽出が可能であることが示唆された。今後、Al(OH)$$_{3}$$の焼成温度の最適化を図り、安定なAl$$_{2}$$O $$_{3}$$を製作する条件を決定する。



大塚 薫; 井手 広史; 永田 寛; 大森 崇純; 関 美沙紀; 花川 裕規; 根本 浩喜; 渡辺 正男; 飯村 光一; 土谷 邦彦; et al.

UTNL-R-0499, p.12_1 - 12_8, 2019/03

材料試験炉(JMTR: Japan Materials Testing Reactor、以下、「JMTR」と言う)は、昭和43年に初臨界を達成して以来、発電用軽水炉燃料や材料の照射試験を中心に、新型転換炉, 高速炉, 高温ガス炉, 核融合炉などの燃料・材料の照射試験に広く利用されてきた。平成29年4月に公表された「施設中長期計画」において、JMTRは廃止施設として決定し、平成30年度末までに廃止措置計画認可申請書を原子力規制庁へ申請することとなり、廃止措置の準備のための組織変更、申請書作成に必要な各種評価を行った。本発表は、作成した廃止措置計画認可申請書に記載する主な評価結果と廃止措置に向けた技術開発課題について報告する。


Off-gas processing system operations for mercury target vessel replacement at J-PARC

甲斐 哲也; 内田 敏嗣; 木下 秀孝; 関 正和; 大井 元貴; 涌井 隆; 羽賀 勝洋; 春日井 好己; 高田 弘

Journal of Physics; Conference Series, 1021(1), p.012042_1 - 012042_4, 2018/06

 被引用回数:0 パーセンタイル:100

At J-PARC an Off-gas processing system has been utilized to a purging process before the target vessel replacement and an air-flow control procedure to minimize radioactivity release during the replacement. In 2011 the first replacement was carried out after a 500 MWh operation, and the tritium release was measured. It was suggested that the tritium release must be less than that measured at the replacement in 2011 even at the nominal operation of 5,000 MWh. Some procedures of an air-flow control and a rubber plug insertion have been introduced from the replacements in 2013, resulting that the amount of tritium release could be reduced to less than that released in 2011 at the nominal operation.



齊藤 宏; 野澤 隆; 武宮 博; 関 暁之; 松原 武史; 斎藤 公明; 北村 哲浩

JAEA-Review 2017-040, 34 Pages, 2018/03




Fabrication and short-term irradiation behaviour of Am-bearing MOX fuels

木原 義之; 田中 康介; 小山 真一; 吉持 宏; 関 崇行; 勝山 幸三

NEA/NSC/R(2017)3, p.341 - 350, 2017/11




小島 真由美*; 城 鮎美*; 鈴木 裕士; 井上 純哉*; 菖蒲 敬久; 徐 平光; 秋田 貢一; 南部 将一*; 小関 敏彦*

材料, 66(6), p.420 - 426, 2017/06

The strain distribution in a multilayered steel composite, which consists of martensite and austenite layers, was evaluated by energy dispersive X-ray diffraction to investigate the homogeneity of deformation in the martensite layer under uniaxial loading. A dog-bone shape specimen with a martensite layer with 0.2 mm in a thickness, sandwiching by austenite layers with 0.4 mm in thickness, was utilized in this study. A change in strains as a function of tensile loading was measured at the center of the martensite layer as well as near the interface between the martensite and austenite layers. Furthermore, the residual strain distributions were measured in the martensite layer of the unloaded specimens after different applied strains. As a result, slight inhomogeneous deformation was found at the beginning of the plastic deformation in the martensite layer although no local deformation was recognized even near the interface between austenite and martensite layers. After further deformation, mismatch of plastic deformation between austenite and martensite layers was reduced, and the martensite layer deformed homogeneously. Therefore, an unstable interface phenomenon might not be caused by the intrinsic factors with a mesoscopic scale discussed in this experiment.


Radiation response of silicon carbide metal-oxide-semiconductor transistors in high dose region

大島 武; 横関 貴史; 村田 航一; 松田 拓磨; 三友 啓; 阿部 浩之; 牧野 高紘; 小野田 忍; 土方 泰斗*; 田中 雄季*; et al.

Japanese Journal of Applied Physics, 55(1S), p.01AD01_1 - 01AD01_4, 2016/01

 被引用回数:7 パーセンタイル:43.28(Physics, Applied)

In this study, we report the effects of $$gamma$$-ray irradiation and subsequent annealing on the electrical characteristics of vertical structure power 4H Silicon Carbide (SiC) Metal-Oxide-Semiconductor Field Effect Transistors (MOSFETs) with the blocking voltage of 1200 V. The MOSFETs were irradiated with $$gamma$$-rays up to 1.2 MGy in a N$$_{2}$$ atmosphere at room temperature (RT). During the irradiation, no bias was applied to each electrode of the MOSFETs. After the irradiation, the MOSFETs were kept at RT for 240 h to investigate the stability of their degraded characteristics. Then, the irradiated MOSFETs were annealed up to 360 $$^{circ}$$C in the atmosphere. The current-voltage (I-V) characteristics of the MOSFETs were measured at RT. By 1.2 MGy irradiation, the shift of threshold voltage (V$$_{T}$$) for the MOSFETs was -3.39 V. After RT preservation for 240 h, MOSFETs showed no significant recovery in V$$_{T}$$. By annealing up to 360 $$^{circ}$$C, the MOSFETs showed remarkable recovery, and the values of V$$_{T}$$ become 91 % of the initial values. Those results indicate that the degraded characteristics of SiC MOSFETs can be recovered by thermal annealing at 360 $$^{circ}$$C.


Recovery of the electrical characteristics of SiC-MOSFETs irradiated with gamma-rays by thermal treatments

横関 貴史; 阿部 浩之; 牧野 高紘; 小野田 忍; 田中 雄季*; 神取 幹郎*; 吉江 徹*; 土方 泰斗*; 大島 武

Materials Science Forum, 821-823, p.705 - 708, 2015/07

Since silicon carbide (SiC) has high radiation resistance, it is expected to be applied to electronic devices used in harsh radiation environments, such as nuclear facilities. Especially, extremely high radiation resistant devices (MGy order) are required for decommissioning of TEPCO Fukushima Daiichi nuclear reactors. The development of radiation resistant devices based on Metal-Oxide-Semiconductor (MOS) FETs is important since MOSFETs can easily realize normally-off and low-loss power devices. In this study, we irradiated vertical power 4H-SiC MOSFETs with gamma-rays up to 1.2 MGy, and investigated the recovery of their degraded characteristics due to thermal annealing up to 360 $$^{circ}$$C. The drain current (I$$_{D}$$) - gate voltage (V$$_{G}$$) curves of SiC MOSFETs shift to the negative voltage side and the leakage of I$$_{D}$$ increased by irradiation at 1.2 MGy. After the irradiation, the MOSFETs were kept at RT for 240 h. By the RT-annealing, no significant change in the degraded electrical characteristics of SiC MOSFETs was observed. The degraded characteristics of SiC MOSFETs began to recover by annealing above 120 $$^{circ}$$C, and their characteristics reach almost the initial ones by annealing at 360 $$^{circ}$$C.


Development of a software platform for providing environmental monitoring data for the Fukushima Daiichi nuclear accident

関 暁之; 斎藤 税; 名古 玄天*; 鈴木 健太; 冨島 一也; 斎藤 公明; 武宮 博

Radiation Protection Dosimetry, 164(1-2), p.97 - 102, 2015/04

 被引用回数:2 パーセンタイル:69.57(Environmental Sciences)



福島周辺における空間線量率の測定と評価,4; 環境中における空間線量率測定の実際

津田 修一; 吉田 忠義; 安藤 真樹; 松田 規宏; 三上 智; 谷垣 実*; 奥村 良*; 高宮 幸一*; 佐藤 信浩*; 関 暁之; et al.

Radioisotopes, 64(4), p.275 - 289, 2015/04



Detailed deposition density maps constructed by large-scale soil sampling for $$gamma$$-ray emitting radioactive nuclides from the Fukushima Dai-ichi Nuclear Power Plant accident

斎藤 公明; 谷畑 勇夫*; 藤原 守; 齊藤 敬*; 下浦 享*; 大塚 孝治*; 恩田 裕一*; 星 正治*; 池内 嘉宏*; 高橋 史明; et al.

Journal of Environmental Radioactivity, 139, p.308 - 319, 2015/01

 被引用回数:136 パーセンタイル:0.52(Environmental Sciences)

The soil deposition density maps of $$gamma$$-ray emitting radioactive nuclides from the Fukushima Daiichi Nuclear Power Plant (NPP) accident were constructed on the basis of the results from large-scale soil sampling. The 10,915 soil samples were collected at 2,168 locations. $$gamma$$-rays emitted from the samples were measured by Ge detectors and analyzed using a reliable unified method. The determined radioactivity was corrected to that as of June 14, 2011 by taking into account the intrinsic decay constant of each nuclide. Finally the maps were created for $$^{134}$$Cs, $$^{137}$$Cs, $$^{131}$$I, $$^{129m}$$Te and $$^{110m}$$Ag. The radioactivity ratio of $$^{134}$$Cs to $$^{137}$$Cs was almost constant as 0.91 irrelevant to the soil sampling location. Effective doses for 50 years after the accident were evaluated for external and inhalation exposures due to the observed radioactive nuclides. The radiation doses from radioactive cesium were found to be much higher than those from other radioactive nuclides.


R&D status on water cooled ceramic breeder blanket technology

榎枝 幹男; 谷川 尚; 廣瀬 貴規; 中島 基樹; 佐藤 聡; 落合 謙太郎; 今野 力; 河村 繕範; 林 巧; 山西 敏彦; et al.

Fusion Engineering and Design, 89(7-8), p.1131 - 1136, 2014/10

 被引用回数:17 パーセンタイル:9.63(Nuclear Science & Technology)



Development of radionuclide distribution database and map system on the Fukushima nuclear accident

関 暁之; 武宮 博; 高橋 史明; 斎藤 公明; 田中 圭*; 高橋 悠*; 竹村 和広*; 津澤 正晴*

Progress in Nuclear Science and Technology (Internet), 4, p.47 - 50, 2014/04



化学形に着目した破損燃料からの核分裂生成物及びアクチニドの放出挙動評価; 溶融被覆管と照射済MOX燃料の反応による相状態とFP放出挙動

田中 康介; 三輪 周平; 佐藤 勇; 廣沢 孝志; 関根 伸一; 関 崇行*; 所 大志郎*; 大林 弘; 小山 真一

JAEA-Research 2013-022, 62 Pages, 2014/01





津田 修一; 吉田 忠義; 中原 由紀夫; 佐藤 哲朗; 関 暁之; 松田 規宏; 安藤 真樹; 武宮 博; 谷垣 実*; 高宮 幸一*; et al.

JAEA-Technology 2013-037, 54 Pages, 2013/10




R&D activities on manufacturing plasma-facing unit for prototype of ITER divertor outer target in JADA

江里 幸一郎; 鈴木 哲; 関 洋治; 西 宏; 毛利 憲介; 榎枝 幹男

Fusion Engineering and Design, 87(7-8), p.1177 - 1180, 2012/08

 被引用回数:5 パーセンタイル:50.74(Nuclear Science & Technology)




重富 洋志*; 岡 潔; 大井 豪一*; 古川 直人*; 吉田 昭三*; 川口 龍二*; 永井 景*; 春田 祥治*; 柳瀬 康仁*; 赤坂 珠理晃*; et al.

日本レーザー医学会誌, 33(2), p.131 - 135, 2012/08




酒井 健二; 坂元 眞一; 木下 秀孝; 関 正和; 羽賀 勝洋; 粉川 広行; 涌井 隆; 直江 崇; 春日井 好己; 達本 衡輝; et al.

JAEA-Technology 2011-039, 121 Pages, 2012/03



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