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Chemical-pressure-induced point defects enable low thermal conductivity for Mg$$_{2}$$Sn and Mg$$_{2}$$Si single crystals

齋藤 亘*; 林 慶*; Huang, Z.*; 杉本 和哉*; 大山 研司*; 八方 直久*; 原田 正英; 及川 健一; 稲村 泰弘; 林 好一*; et al.

ACS Applied Energy Materials (Internet), 4(5), p.5123 - 5131, 2021/05

 被引用回数:10 パーセンタイル:71.73(Chemistry, Physical)

The development of thermoelectric (TE) materials, which can directly convert waste heat into electricity, is vital to reduce the use of fossil fuels. Mg$$_{2}$$Sn and Mg$$_{2}$$Si are promising TE materials because of their superior TE performance. In this study, for future improvement of the TE performance, point defect engineering was applied to the Mg$$_{2}$$Sn and Mg$$_{2}$$Si single crystals (SCs) via boron (B) doping. Their crystal structures were analyzed via white neutron holography and SC X-ray diffraction. Moreover, nanostructures and TE properties of the B-doped Mg$$_{2}$$Sn and Mg$$_{2}$$Si SCs were investigated. The B-doping increased the chemical pressure on the Mg$$_{2}$$Sn and Mg$$_{2}$$Si SCs, leading to induce vacancy defects as a point defect. No apparent change was observed in electronic transport, but thermal transport was significantly prevented. This study demonstrates that the vacancy defects can be controlled by the chemical pressure, and can aid in achieving a high TE performance for the Mg$$_{2}$$Sn and Mg$$_{2}$$Si SCs.


Preparation, thermoelectric properties, and crystal structure of boron-doped Mg$$_{2}$$Si single crystals

林 慶*; 齋藤 亘*; 杉本 和哉*; 大山 研司*; 林 好一*; 八方 直久*; 原田 正英; 及川 健一; 稲村 泰弘; 宮崎 譲*

AIP Advances (Internet), 10(3), p.035115_1 - 035115_7, 2020/03

 被引用回数:16 パーセンタイル:77.96(Nanoscience & Nanotechnology)

Mg$$_{2}$$Si is a potential thermoelectric (TE) material that can directly convert waste energy into electricity. In expectation of improving its TE performance by increasing electron carrier concentration, the element boron (B) is doped in Mg$$_{2}$$Si single crystals (SCs). Their detailed crystal structures are definitely determined by using white neutron holography and single-crystal X-ray diffraction (SC-XRD) measurements. The white neutron holography measurement proves that the doped B atom successfully substitutes for the Mg site. The SC-XRD measurement confirms the B-doping site and also reveals the presence of the defect of Si vacancy (VSi) in the B-doped Mg$$_{2}$$Si SCs. Regarding TE properties, the electrical conductivity, $$sigma$$, and the Seebeck coefficient, S, decreases and increases, respectively, due to the decrease in the electron carrier concentration, contrary to the expectation. The power factor of the B-doped Mg$$_{2}$$Si SCs evaluated from $$sigma$$ and S does not increase but rather decreases by the B-doping.


Nitrogen hot trap design and manufactures for lithium test loop in IFMIF/EVEDA project

若井 栄一; 渡辺 一慶*; 伊藤 譲*; 鈴木 晶大*; 寺井 隆幸*; 八木 重郎*; 近藤 浩夫; 金村 卓治; 古川 智弘; 平川 康; et al.

Plasma and Fusion Research (Internet), 11, p.2405112_1 - 2405112_4, 2016/11


The lithium target facility of IFMIF (International Fusion Materials Irradiation Facility) consists of target assembly, lithium main loop, lithium purification loops, the diagnostic systems, and remote handling system. Major impurities in the lithium loop are proton, deuterium, tritium, 7-Be, activated corrosion products and the other species (C, N, O). It is very important to remove nitrogen content in lithium loop during operation, in order to avoid the corrosion/erosion of the nozzle of lithium target for the stable lithium flow on the target assembly. Nitrogen in the lithium can be removed by N hot trap using Fe-5at%Ti alloy at temperatures from 400 to 600$$^{circ}$$C. In this study, the specification and the detailed design were evaluated, and the component of N hot trap system was fabricated.


Numerical study on influence of Ohnesorge number and Reynolds number on the jet breakup behavior using the lattice Boltzmann method

岩澤 譲*; 阿部 豊*; 金子 暁子*; 金川 哲也*; 齋藤 慎平*; 松尾 英治*; 海老原 健一; 坂場 弘*; 小山 和也*; 成合 英樹*

Proceedings of 23rd International Conference on Nuclear Engineering (ICONE-23) (DVD-ROM), 7 Pages, 2015/05



Crack growth behavior of F82H steel in the 288$$^{circ}$$C water

伊藤 譲; 齋藤 正博*; 阿部 勝憲*; 若井 栄一

Journal of Plasma and Fusion Research SERIES, Vol.11, p.73 - 78, 2015/03

き裂成長は、核融合の実証炉用構造材料を設計・評価する上で重要な機械的特性の一つであり、国際核融合材料照射施設(IFMIF)の高中性子束テストモジュール(HFTM)にてき裂成長が評価されることになっている。本研究では、き裂成長に及ぼす試験片の寸法効果を避けるため、ほぼ標準サイズの試験片を用いて288$$^{circ}$$C水中におけるF82H鋼のき裂進展速度を評価した。試験片の破面を観察した結果、288$$^{circ}$$C水中ではなく室温大気中で疲労き裂が進展した領域でも、き裂が粒界を進展した結果の粒界割れ破面を得た。粒界割れ破面が得られる原因の一つは、F82H鋼の粒界に析出したクロム炭化物Cr$$_{23}$$C$$_{6}$$の影響と推測された。また、288$$^{circ}$$C水中で進展したように見えるき裂が観察された。き裂進展速度を保守的に評価した結果、き裂先端の応力場を示すパラメータの応力拡大係数30MPa $$sqrt[]{m}$$において、288$$^{circ}$$C水中のき裂進展速度7$$times$$10$$^{-11}$$m/sを得た。今後は、より系統的な試験の実施と共に、き裂が進展しないような表面処理等の工夫が必要であると考えられる。


Effect of hydrogen on crack growth behavior in F82H steel using small-size specimen

伊藤 譲; 齋藤 正博*; 阿部 勝憲*; 若井 栄一

Small Specimen Test Techniques; 6th Volume (ASTM STP 1576), p.209 - 224, 2015/00

Crack growth is a one of the key mechanical properties of the design evaluation in fusion materials to be tested at the High Flux Test Module (HFTM) in IFMIF. In the IFMIF/EVEDA project under the BA agreement, effect of hydrogen on the crack growth in F82H steel was investigated by using the relatively small size specimen. The shape of an Wedge Opening Load (WOL) specimen is adapted as a miniaturized specimen because the loading mechanism of WOL specimen is relatively simple compared to that of the other notched specimen. The hydrogen charging process was conducted for about 600 hours in the electrolytic solution with the current density of -2 mA/cm$$^{2}$$ at 35$$^{circ}$$C. And then, the testing load, ${it K}$ = 30 MPa$$sqrt{m}$$, was applied to the specimen for about 337 hours at room temperature in air as the crack growth rate test. From these results, the small size specimen used in this study is thought to be adequate to evaluate the effect of hydrogen on the crack behavior in F82H steel.



若井 栄一; 近藤 浩夫; 金村 卓治; 平川 康; 古川 智弘; 帆足 英二*; 深田 智*; 鈴木 晶大*; 八木 重郎*; 辻 義之*; et al.

Proceedings of Plasma Conference 2014 (PLASMA 2014) (CD-ROM), 2 Pages, 2014/11



Engineering validation and engineering design of lithium target facility in IFMIF/EVEDA project

若井 栄一; 近藤 浩夫; 金村 卓治; 古川 智弘; 平川 康; 渡辺 一慶; 井田 瑞穂*; 伊藤 譲; 新妻 重人; 枝尾 祐希; et al.

Fusion Science and Technology, 66(1), p.46 - 56, 2014/07

 被引用回数:4 パーセンタイル:32.11(Nuclear Science & Technology)

EVEDA Lithium Test Loop (ELTL) has been designed and constructed, has operated a liquid lithium flow test facility with the world's highest flow rate and has succeeded in generating a 100-mm-wide and 25-mm-thick free-surface lithium flow along a concave back plate steadily at a high speed of 20 m/s at 300$$^{circ}$$C for the first time in the world. This result will greatly advance the development of an accelerator-based neutron source to high energy and high density, one of the key objectives of the fusion reactor materials development under the BA (Broader Approach) Activities. Recent related engineering validation and engineering design of the lithium facility has been evaluated.


Thermal stability of butt joint for CS conductor in JT-60SA

高尾 智明*; 川原 譲*; 中村 一也*; 山本 侑祐*; 谷貝 剛*; 村上 陽之; 吉田 清; 夏目 恭平*; 濱口 真司*; 尾花 哲浩*; et al.

IEEE Transactions on Applied Superconductivity, 24(3), p.4800804_1 - 4800804_4, 2014/06

 被引用回数:3 パーセンタイル:22.41(Engineering, Electrical & Electronic)

JT-60SAの中心ソレノイド(CS)は、6つの8層パンケーキコイルと1つの4層パンケーキコイルから構成される。パンケーキコイル間の接続は、プラズマへ供給する磁束を大きくするために、省スペースで設置が可能なITER-EDAのCSモデルコイルで開発された突合せ接続により行われる。本研究ではCS用突合せ接続サンプルを用いて、通電電流値,超臨界圧ヘリウム(SHe)流量, SHe圧力,外部磁場を変化させクエンチ温度(Tq)を測定した。また有限要素法(FEM)解析ソフトCOMSOL Multiphysicsを用いてCS突合せ接続内の温度上昇及び温度分布の数値計算を実施した。これらの試験と解析の結果、CS突合せ接続部はSHe流量が減少しても安定に運転できることがわかった。本論文では、Tq測定試験やFEM解析モデル及びCS接続部のTqとSHe流量の評価結果について報告する。


Influence of fragmentation on jet breakup behaviour

岩澤 譲*; 阿部 豊*; 金子 暁子*; 黒田 泰平*; 松尾 英治*; 海老原 健一; 坂場 弘*; 小山 和也*; 伊藤 和宏*; 成合 英樹*

Proceedings of 15th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-15) (USB Flash Drive), 12 Pages, 2013/05



Development of small specimen test techniques for the IFMIF test cell

若井 栄一; Kim, B. J.; 野澤 貴史; 菊地 孝行; 平野 美智子*; 木村 晃彦*; 笠田 竜太*; 横峯 健彦*; 吉田 崇英*; 野上 修平*; et al.

Proceedings of 24th IAEA Fusion Energy Conference (FEC 2012) (CD-ROM), 6 Pages, 2013/03

Recent progress of small specimen test technique and the engineering design and engineering validation tests of high flux test module (HFTM) for the IFMIF test cell is mainly summarized and evaluated in the IFMIF/EVEDA (Engineering validation and engineering design activities) projects under Broader Approach Agreement between EURATOM and Japan. Effects of specimen size on mechanical properties such as impact properties and ductile-to-brittle transition temperature are known to occur in ferritic/martensitic steels, and some parts of them have been prepared in the guideline and standard of mechanical tests by ASTM-international and ISO. However, our research of ferritic/martensitic steel F82H showed that it did not match with our data, i.e., master curve method for fracture in ductile-to-brittle transition behaviour of F82H steel. Accordingly, we need to modify and develop these standards for the tests including small size specimens of fusion materials in IFMIF. Also, some designs were prepared in the design of HFTM.


Observation of the partial Fermi surface quenching in the noncentrosymmetric superconductor Mo$$_3$$Al$$_2$$C

小山 岳秀*; 尾崎 穣*; 上田 光一*; 水戸 毅*; 小原 孝夫*; 和氣 剛*; 田畑 吉計*; 道岡 千城*; 吉村 一良*; 鈴木 通人; et al.

Journal of the Physical Society of Japan, 81(Suppl.B), p.SB008_1 - SB008_5, 2012/12

 被引用回数:1 パーセンタイル:11.02(Physics, Multidisciplinary)



高速炉におけるガス巻込み現象の防止基準,1; 数値解析によるガス巻込み現象再現精度の検証

大島 宏之; 田中 伸厚*; 江口 譲*; 西村 元彦*; 功刀 資彰*; 内堀 昭寛; 伊藤 啓; 堺 公明

日本原子力学会和文論文誌, 11(4), p.316 - 328, 2012/12



高速炉におけるガス巻込み現象の防止基準,2; ガス巻込み発生判定手法の提案

大島 宏之; 江口 譲*; 功刀 資彰*; 上出 英樹; 堺 公明; 伊藤 啓

日本原子力学会和文論文誌, 11(4), p.329 - 339, 2012/12



Partial gap opening on the Fermi surface of the noncentrosymmetric superconductor Mo$$_3$$Al$$_2$$C

小山 岳秀*; 尾崎 穣*; 上田 光一*; 水戸 毅*; 小原 孝夫*; 和気 剛*; 田畑 吉計*; 道岡 千城*; 吉村 一良*; 鈴木 通人; et al.

Physical Review B, 84(21), p.212501_1 - 212501_4, 2011/12

 被引用回数:11 パーセンタイル:45.31(Materials Science, Multidisciplinary)



Small specimen test technology and methodology of IFMIF/EVEDA and the further subjects

若井 栄一; 野上 修平*; 笠田 竜太*; 伊藤 譲*; 高田 文樹; 他6名*

Journal of Nuclear Materials, 417, p.1325 - 1330, 2011/10

 被引用回数:25 パーセンタイル:87.16(Materials Science, Multidisciplinary)

About one thousands of small size specimens will be irradiated in the High Flux Test Module (HFTM) in a limited volume of 0.5 liter in the International Fusion Materials Irradiation Facility (IFMIF). It is necessary to verify that the experimental data of these small specimens about mechanical characterization can be safely extrapolated to standard specimens data, enabling a sound dimensioning of DEMO reactor. The program of Small Size Test Technique (SSTT) in IFMIF/EVEDA (Engineering Validation and Engineering Design Activity) phase for fatigue, fracture toughness and crack growth measurement is summarized, and recent progress and some analysis of the experiments have performed for small size specimens.


Improvement of gas entrainment prediction method; Introduction of surface tension effect

伊藤 啓; 堺 公明; 江口 譲*; 文字 秀明*; 大島 宏之; 内堀 昭寛; Xu, Y.*

Journal of Nuclear Science and Technology, 47(9), p.771 - 778, 2010/09

 被引用回数:12 パーセンタイル:60.23(Nuclear Science & Technology)



Improvement of gas entrainment evaluation method; Introduction of surface tension effect

伊藤 啓; 江口 譲*; 文字 秀明*; 大島 宏之; 内堀 昭寛; Xu, Y.*

Proceedings of 6th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-6) (USB Flash Drive), 8 Pages, 2008/11



Proposal of design criteria for gas entrainment from vortex dimples based on a computational fluid dynamics method

堺 公明; 江口 譲*; 文字 秀明*; 伊藤 啓; 大島 宏之

Heat Transfer Engineering, 29(8), p.731 - 739, 2008/08

 被引用回数:37 パーセンタイル:80.73(Thermodynamics)



「数値解析による自由液面からのガス巻込み評価指針」の解説, 解説B(協力研究)

大島 宏之; 堺 公明; 上出 英樹; 木村 暢之; 江連 俊樹; 内堀 昭寛; 伊藤 啓; 功刀 資彰*; 岡本 孝司*; 田中 伸厚*; et al.

JAEA-Research 2008-049, 44 Pages, 2008/06



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