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A Design study on a mixed oxide fuel sodium-cooled fast reactor core partially loading highly concentrated MA-containing metal fuel

大釜 和也; 太田 宏一*; 大木 繁夫; 飯塚 政利*

Proceedings of 2019 International Congress on Advances in Nuclear Power Plants (ICAPP 2019) (Internet), 9 Pages, 2019/05

A neutronics design study for a mixed oxide (MOX) fuel Sodium-cooled Fast Reactor (SFR) core partially loading highly concentrated Minor Actinide (MA) containing fuel was conducted. To analyze preferable loading positions of highly concentrated MA-containing metal fuel, the characteristics of heterogeneous MA loading cores were evaluated assuming the amount of MA loaded to heterogeneous cores were same as that of a reference homogeneous 3% MAcontaining MOX fuel core. The cores loading MA-containing metal fuel could meet the design limitation of the sodium void reactivity of the SFR except for the one loading MA-containing metal fuel in the core center region. Based on these results, the core design was modified to maximize amount of MA transmutation. The modified core loading 60 subassemblies of 16% MA-containing metal fuel in the outermost region could attain the largest amount of MA transmutation, which was larger by about 60% than that of the reference homogeneous MOX fuel core.


Design study of a 750 MWe Japan sodium-cooled fast reactor with metal fuel

大釜 和也; 太田 宏一*; 生澤 佳久; 大木 繁夫; 尾形 孝成*

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

Under the collaborative research of Central Research Institute of Electric Power Industry (CRIEPI) and Japan Atomic Energy Agency (JAEA), the metal fuel core concept has been studied. In this study, a 750 MWe sodium-cooled fast reactor (SFR) with metal fuel designed in a past/precedent study was reevaluated considering the irradiation behaviors of metal fuel such as axial elongation and bond-sodium redistribution, which have significant impacts on the core characteristics such as the multiplication factor and sodium void reactivity worth. The result of reanalysis indicated that the sodium void reactivity worth of the core became higher than that evaluated in the past study, so the redesign of the core was performed to improve the sodium void reactivity worth. To redesign the core, correlations of the sodium void reactivity worth and the dimension of the core and fuel subassemblies was investigated by survey calculations. Based on the results, specifications of the redesigned core were selected. The characteristics of the redesign core were evaluated. To verify the deterministic calculation results, the core characteristics of the redesign core were compared with those by a contentious-energy Monte Carlo simulation with precise geometry modeling, which can provide reference solutions. The both calculations agreed well, and the improvements of core characteristics of the redesign core were verified.



佐藤 稔紀; 笹本 広; 石井 英一; 松岡 稔幸; 早野 明; 宮川 和也; 藤田 朝雄*; 棚井 憲治; 中山 雅; 武田 匡樹; et al.

JAEA-Research 2016-025, 313 Pages, 2017/03




Development of accident tolerant control rod for light water reactors

太田 宏一*; 中村 勤也*; 尾形 孝成*; 永瀬 文久

Proceedings of Annual Topical Meeting on LWR Fuels with Enhanced Safety and Performance (TopFuel 2016) (USB Flash Drive), p.159 - 168, 2016/09



Dipole tracer migration and diffusion tests in fractured sedimentary rock at Horonobe URL

田中 真悟*; 横田 秀晴; 大野 宏和; 中山 雅; 藤田 朝雄; 瀧谷 啓晃*; 渡辺 直子*; 小崎 完*

Proceedings of 23rd International Conference on Nuclear Engineering (ICONE-23) (DVD-ROM), 6 Pages, 2015/05

In-situ dipole tracer migration tests were conducted at the G.L.-250 m gallery of the Horonobe URL. Laboratory experiments were also conducted to determine the apparent diffusivity (${{it D$_{a}$}}$) and sorption coefficients (${{it K$_{d}$}}$) of cesium and water (HTO) in the rock taken at the gallery to evaluate the performance of Wakkanai formation as natural barrier. The breakthrough curves of non-sorbing tracer (Uranine) obtained at the in-situ dipole tracer migration tests were well described by a dual-channel model in which one-dimensional advection dispersion was taken in account. This suggests that the tracers migrate through at least two different pathways in the fracture. The breakthrough curves also indicated that the peak concentration of the sorbing tracer (cesium) was much smaller than that of the non-sorbing tracer (Uranine), suggesting that the Wakkanai Formation has a high sorptive and low diffusive properties for cesium. The ${{it D$_{a}$}}$ value obtained for cesium was about 3E-12 m$$^{2}$$/s, which is significantly smaller than that of water (3E-10 m$$^{2}$$/s), and the ${{it K$_{d}$}}$ value of cesium was determined to be about 5E-2 ml/g.


金属燃料高速炉の炉心・燃料設計に関する研究(4),(5)及び(6); 2009-2012年度共同研究報告書

植松 眞理 マリアンヌ; 杉野 和輝; 川島 克之; 岡野 靖; 山路 哲史; 永沼 正行; 大木 繁夫; 大久保 努; 太田 宏一*; 尾形 孝成*; et al.

JAEA-Research 2012-041, 126 Pages, 2013/02




Tilted-foil technique for producing a spin-polarized radioactive isotope beam

平山 賀一*; 三原 基嗣*; 渡辺 裕*; Jeong, S. C.*; 宮武 宇也*; 百田 佐多夫*; 橋本 尚志*; 今井 伸明*; 松多 健策*; 石山 博恒*; et al.

European Physical Journal A, 48(5), p.54_1 - 54_10, 2012/05

 被引用回数:2 パーセンタイル:77.83(Physics, Nuclear)

The tilted-foil method for producing spin-polarized radioactive isotope beams has been studied for the application to nuclear physics and materials science, using the radioactive nucleus $$^8$$Li produced at the Tokai Radioactive Ion Accelerator Complex (TRIAC). We successfully produced polarization in a $$^8$$Li beam using 15 thin polystyrene foils fabricated especially for this purpose. A systematic study of the nuclear polarization as a function of the number of foils, beam energy, tilt angles and foil material has been performed, confirming the features of the tilted-foil technique experimentally. The contributions made to the nuclear polarization of $$^8$$Li nuclei by the atomic states was investigated.


Actinide-handling experience for training and education of future expert under J-ACTINET

逢坂 正彦; 小無 健司*; 林 博和; Li, D.*; 本間 佳哉*; 山村 朝雄*; 佐藤 勇; 三輪 周平; 関本 俊*; 窪田 卓見*; et al.

Proceedings of International Conference on Toward and Over the Fukushima Daiichi Accident (GLOBAL 2011) (CD-ROM), 5 Pages, 2011/12



Relationship between hypocentral distribution and geological structure in the Horonobe area, northern Hokkaido, Japan

常盤 哲也; 浅森 浩一; 平賀 正人*; 山田 治; 森谷 祐一*; 堀田 光*; 北村 至*; 横田 秀晴

Proceedings of 13th International Conference on Environmental Remediation and Radioactive Waste Management (ICEM 2010) (CD-ROM), p.117 - 122, 2010/10




伊藤 崇; 浅野 博之; 田中 宏和*; 久保田 親*; 南茂 今朝雄*; 内藤 富士雄*

Proceedings of 6th Annual Meeting of Particle Accelerator Society of Japan (CD-ROM), p.690 - 692, 2010/03



Momentum-resolved charge excitations in high-$$T$$$$_{rm c}$$ cuprates studied by resonant inelastic X-ray scattering

石井 賢司; Hoesch, M.*; 稲見 俊哉; 葛下 かおり*; 大和田 謙二; 坪田 雅己; 村上 洋一; 水木 純一郎; 遠藤 康夫; 筒井 健二*; et al.

Journal of Physics and Chemistry of Solids, 69(12), p.3118 - 3124, 2008/12

 被引用回数:3 パーセンタイル:78.44(Chemistry, Multidisciplinary)

Resonant inelastic X-ray scattering (RIXS) in the hard X-ray regime is a new spectroscopic technique to measure electronic excitations utilizing brilliant synchrotron radiation. It has the great advantage that the momentum dependence can be measured unlike conventional optical methods. As inelastic neutron scattering gives spin or lattice dynamics, inelastic X-ray scattering can be a tool to measure charge dynamics in solids through the coupling of photon to the charge of the electron. Here, I would like to present our RIXS studies on high-$$T_c$$ cuprates and related materials which were performed in close collaboration with theorists. In doped Mott insulators, an interband excitation across the Mott gap and an intraband excitation below the gap are observed in the low energy region of RIXS spectra. Momentum and carrier-doping dependence of the excitations will be discussed.



森下 卓俊; 青 寛幸; 伊藤 崇; 上野 彰; 長谷川 和男; 池上 雅紀*; 久保田 親*; 高崎 栄一*; 田中 宏和*; 内藤 富士雄*; et al.

Proceedings of 2nd Annual Meeting of Particle Accelerator Society of Japan and 30th Linear Accelerator Meeting in Japan, p.266 - 268, 2005/07



An Alignment of J-PARC linac

森下 卓俊; 青 寛幸; 伊藤 崇; 上野 彰; 長谷川 和男; 池上 雅紀*; 久保田 親*; 内藤 富士雄*; 高崎 栄一*; 田中 宏和*; et al.

Proceedings of 2005 Particle Accelerator Conference (PAC '05) (CD-ROM), p.2851 - 2853, 2005/00




森下 卓俊; 青 寛幸; 伊藤 崇; 上野 彰; 長谷川 和男; 池上 雅紀*; 久保田 親*; 高崎 栄一*; 田中 宏和*; 内藤 富士男*; et al.

Proceedings of 1st Annual Meeting of Particle Accelerator Society of Japan and 29th Linear Accelerator Meeting in Japan, p.671 - 673, 2004/08



KEKにおけるJ-PARC LINAC DTL1のビームコミッショニング

近藤 恭弘; 秋川 藤志; 穴見 昌三*; 浅野 博之*; 福井 佑治*; 五十嵐 前衛*; 池上 清*; 池上 雅紀*; 伊藤 崇; 川村 真人*; et al.

Proceedings of 1st Annual Meeting of Particle Accelerator Society of Japan and 29th Linear Accelerator Meeting in Japan, p.156 - 158, 2004/08



共同研究報告書 金属燃料高速炉の炉心燃料設計に関する研究(平成12年度)

太田 宏一*; 尾形 孝成*; 横尾 健*; 池上 哲雄; 林 秀行; 水野 朋保; 山館 恵

JNC-TY9400 2001-015, 40 Pages, 2001/03




核燃料に関する計算組織学的な解析技術の開発,1; 研究開発の概要とねらい

倉田 正輝*; 太田 宏一*; 稲垣 健太*; 白数 訓子; 野本 祐春*; 澁田 靖*; 松田 哲志*

no journal, , 




田尻 剛司; 清田 史功; 林 宏一; 香田 有哉

no journal, , 

福井工業大学における「放射性廃棄物工学」講座において、廃止措置を紹介する。講義は、原子力発電所の廃止措置、「ふげん」の廃止措置計画、「ふげん」の廃止措置の状況と題して3回行う。第1回: 廃止措置の制度、国内外の廃止措置の実績廃止措置に必要となる技術、第2回: 「ふげん」の概要、「ふげん」の廃止措置計画の概要、残留放射能評価、安全評価、第3回: 廃止措置における主要技術、系統除染、原子炉本体の遠隔解体技術、「ふげん」の廃止措置に状況と適用した技術


750MWe JSFR金属燃料炉心の設計,2; 炉心核設計

大釜 和也; 太田 宏一*; 生澤 佳久; 大木 繁夫; 尾形 孝成*

no journal, , 



750MWe JSFR金属燃料炉心の設計,1; 燃料照射挙動評価

太田 宏一*; 大釜 和也; 尾形 孝成*; 生澤 佳久; 大木 繁夫

no journal, , 


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