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Modeling the processes of hydrogen isotopes interactions with solid surfaces

Chikhray, Y.*; Askerbekov, S.*; Kenzhin, Y.*; Gordienko, Y.*; 石塚 悦男

Fusion Science and Technology, 76(4), p.494 - 502, 2020/05

 被引用回数:0 パーセンタイル:100(Nuclear Science & Technology)

The investigation of the mechanisms and dynamics of hydrogen isotopic interaction with solid surfaces (metals, ceramics, graphites, eutectics) in temperature and pressure ranges is important not only for the correct prediction of each isotope's evolution but also for substantiation of the safe operation of hydrogen-facing structural materials. The interaction of the hydrogen isotopes mix with the surface of solid metal or liquid eutectics is a complicated multistage H-D-T-O-solid interacting process depending on material property, environment, and the solid's surface parameters. To better understand the mechanisms of hydrogen isotopes interchange at a solid surface and to identify the limiting stages in the sorption-desorption processes, a reactor experiment of neutron irradiation was conducted with lithium-containing eutectics as tritium-generating media under the external flow of hydrogen. This work presents the model and results of its application to fitting the experimental results of tritium yield from the lithium-lead eutectics Pb$$_{83}$$Li$$_{17}$$under thermal neutrons irradiation at the IVG.1M reactor in Kazakhstan. The elaborated model and the approach used were also applied to the simulation of high temperature gas cooled reactor graphite corrosion in water vapors.


Lead benchmark experiment with DT neutrons at JAEA/FNS

権 セロム*; 太田 雅之*; 佐藤 聡*; 今野 力; 落合 謙太郎*

Fusion Science and Technology, 72(3), p.362 - 367, 2017/10

 被引用回数:1 パーセンタイル:78(Nuclear Science & Technology)



Hydrophobic platinum honeycomb catalyst to be used for tritium oxidation reactors

岩井 保則; 久保 仁志*; 大嶋 優輔*; 野口 宏史*; 枝尾 祐希; 谷内 淳一*

Fusion Science and Technology, 68(3), p.596 - 600, 2015/10

 被引用回数:0 パーセンタイル:100(Nuclear Science & Technology)



Effect of helium on irradiation creep behavior of B-doped F82H irradiated in HFIR

安堂 正己; 野澤 貴史; 廣瀬 貴規; 谷川 博康; 若井 栄一; Stoller, R. E.*; Myers, J.*

Fusion Science and Technology, 68(3), p.648 - 651, 2015/10

 被引用回数:1 パーセンタイル:85.53(Nuclear Science & Technology)

照射下クリープに及ぼすヘリウムの影響を調べるために、F82H鋼およびボロン添加したF82H鋼の圧力管を準備し、573Kおよび673Kにて6dpaまでの中性子照射を行った。照射後、これらの圧力管の径を非接触型レーザーシステムにて測定し、クリープひずみの解析を行った。この結果、573K, 673Kにて照射されたF82H鋼のクリープひずみは約260MPaおよび170MPaの応力までそれぞれ直線的に増加することがわかった。特に673K照射材では、いくらかの$$^{10}$$BN添加F82H鋼のクリープひずみは、ヘリウムの発生しない$$^{11}$$BN添加F82H鋼に比べて増加する傾向にあった。この原因として、ボロンによって発生したヘリウムによりバブルが形成し、わずかなスウェリングが生じたためと考えられる。


Evaluation of tritium confinement performance of alumina and zirconium for tritium production in a high-temperature gas-cooled reactor for fusion reactors

片山 一成*; 牛田 宏樹*; 松浦 秀明*; 深田 智*; 後藤 実; 中川 繁昭

Fusion Science and Technology, 68(3), p.662 - 668, 2015/10

 被引用回数:7 パーセンタイル:31.3(Nuclear Science & Technology)



Present status of manufacturing and R&Ds for the JT-60SA tokamak

東島 智; 鎌田 裕; Barabaschi, P.*; 白井 浩; JT-60SAチーム

Fusion Science and Technology, 68(2), p.259 - 266, 2015/09

 被引用回数:0 パーセンタイル:100(Nuclear Science & Technology)

The JT-60SA superconducting tokamak is now under construction toward the first plasma in March 2019 as a joint project between the Broader Approach (BA) Satellite Tokamak Programme of Europe and Japan, and the Japanese national programme. The JT-60SA mission is to contribute to early realization of fusion energy by supporting ITER and by complementing ITER in resolving key physics and engineering issues for DEMO reactors. Before procurements of the major components, some R&Ds for key techniques were performed. By May 2014, 23 procurement arrangements (PAs) have been launched (JA: 13PAs, EU: 10PAs) covering 87% of the total cost of the BA Satellite Tokamak Programme, and the main components have entered the manufacturing stage. In addition, the JT-60SA tokamak assembly started since January 2013. This paper summarizes the recent progress of the JT-60SA project.


Management strategy for radioactive waste in the fusion DEMO reactor

染谷 洋二; 飛田 健次; 宇藤 裕康; 朝倉 伸幸; 坂本 宜照; 星野 一生; 中村 誠; 徳永 晋介

Fusion Science and Technology, 68(2), p.423 - 427, 2015/09

 被引用回数:8 パーセンタイル:26.68(Nuclear Science & Technology)



Study on operation scenario of tritium production for a fusion reactor using a high temperature gas-cooled reactor

川本 靖子*; 中屋 裕行*; 松浦 秀明*; 片山 一成*; 後藤 実; 中川 繁昭

Fusion Science and Technology, 68(2), p.397 - 401, 2015/09

 被引用回数:1 パーセンタイル:85.53(Nuclear Science & Technology)



One-dimensional analysis of ECRH-assisted plasma start-up in JT-60SA

羽田 和慶*; 長崎 百伸*; 増田 開*; 小林 進二*; 井手 俊介; 諫山 明彦; 梶原 健

Fusion Science and Technology, 67(4), p.693 - 704, 2015/05

 被引用回数:5 パーセンタイル:44.04(Nuclear Science & Technology)



Development of ITER equatorial EC launcher components toward the final design

高橋 幸司; 梶原 健; 小田 靖久; 坂本 慶司; 大森 俊道*; Henderson, M.*

Fusion Science and Technology, 67(4), p.718 - 731, 2015/05

 被引用回数:3 パーセンタイル:61.74(Nuclear Science & Technology)

ITER ECランチャーの開発において、ランチャーの機能、信頼性向上を目的とした改良設計やプロトタイプ試験を行ってきた。改良設計では、中性子遮蔽性を高めるべく、ランチャー前方に遮蔽構造物を追加するため、ミリ波伝送部における固定ミラーの位置を後方へずらしつつ、マイクロ波伝送性を保つ設計改良を行った。その設計に基づくマイクロ波伝送部のモックアップを製作し、大電力伝送実験を行った。所定の角度可変範囲(20$$^{circ}$$$$sim$$40$$^{circ}$$)において設計通りのマイクロ波伝送を実証すると共に、散乱マイクロ波によりビームダクト内壁の温度上昇を観測し、散乱マイクロ波に対するビームダクトの冷却性能の必要性を明らかにした。また、ブランケットやポートプラグについて、主に、製作性と冷却水の流力特性を評価するためのモックッアップを製作した。ブランケットやポートプラグの製作で想定しているHIPや溶接施工性などにおける大きな技術課題は無く、また、冷却設計においては、設計要求通りの圧力損失内で必要な流量が確保できることを実験的に明らかにした。


Effect of tritium on corrosion behavior of chromium in 0.01N sulfuric acid solution

小柳津 誠; 磯部 兼嗣; 林 巧

Fusion Science and Technology, 67(3), p.519 - 522, 2015/04

 被引用回数:2 パーセンタイル:73.04(Nuclear Science & Technology)



Evaluation of tritium release properties of advanced tritium breeders

星野 毅; 落合 謙太郎; 枝尾 祐希; 河村 繕範

Fusion Science and Technology, 67(2), p.386 - 389, 2015/03

 被引用回数:8 パーセンタイル:26.68(Nuclear Science & Technology)



Recent progress on tritium technology research and development for a fusion reactor in Japan Atomic Energy Agency

林 巧; 中村 博文; 河村 繕範; 岩井 保則; 磯部 兼嗣; 山田 正行; 鈴木 卓美; 倉田 理江; 小柳津 誠; 枝尾 祐希; et al.

Fusion Science and Technology, 67(2), p.365 - 370, 2015/03

 被引用回数:0 パーセンタイル:100(Nuclear Science & Technology)

Tritium Process Laboratory (TPL) of Japan Atomic Energy Agency (JAEA) was constructed in1985, and started in 1988, in order to develop key technologies for fusion fuel cycle, and also to demonstrate safety handling technologies. TPL has a license, which can handle 9.25 PBq of tritium per day and store 22.2 PBq of total tritium. DEMO Design and R&D building was also newly constructed at Rokkasho-Aomori establishment of JAEA in 2011. This R&D building has a license, which can handle 3.7 TBq of tritium per day and store 7.4 TBq of total tritium, and also can handle other major neutron induced radioactive isotopes. Recently, our activities have been focused as follows; (1) Detritiation system R&D as an ITER task, specially for wet scrubber column development as a pilot scale; (2) Tritium tasks of DEMO R&D in the IFERC project of BA activities, such as (a) tritium accountancy, (b) tritium interactions with various materials, which will be used for DEMO, and (c) tritium durability; (3) Recovery works from the 2011 earthquake and tsunami in Tohoku japan: This paper summarizes the above recent progress of tritium technology R&D for fusion reactor in JAEA and summarized also the lessons of learned through the recovery & maintenance work after the earthquake.


Measurement of tritium penetration through concrete material covered by various paints coating

枝尾 祐希; 河村 繕範; 倉田 理江; 深田 智*; 竹石 敏治*; 林 巧; 山西 敏彦

Fusion Science and Technology, 67(2), p.320 - 323, 2015/03

 被引用回数:0 パーセンタイル:100(Nuclear Science & Technology)



Behavior of tritium in the vacuum vessel of JT-60U

小林 和容; 鳥養 祐二*; 齋藤 真貴子; Alimov, V. Kh.*; 宮 直之; 池田 佳隆

Fusion Science and Technology, 67(2), p.428 - 431, 2015/03

 被引用回数:0 パーセンタイル:100(Nuclear Science & Technology)



Correlation of rates of tritium migration through porous concrete

深田 智*; 片山 一成*; 竹石 敏治*; 枝尾 祐希; 河村 繕範; 林 巧; 山西 敏彦

Fusion Science and Technology, 67(2), p.99 - 102, 2015/03

 被引用回数:0 パーセンタイル:100(Nuclear Science & Technology)

What affects tritium migration through porous concrete walls coated with a hydrophobic paint is reviewed from the viewpoint of tritium safety. Being taken into consideration of multi-structural concrete composed of aggregates, sand, water and cement which contents are CaO, SiO$$_{2}$$, Al$$_{2}$$O$$_{3}$$, Fe$$_{2}$$O$$_{3}$$, MgO, CaSO$$_{4}$$ and so on, tritium path is discussed in terms of the HTO diffusivity and adsorption coeffcient on porous walls. Measures to predict rates of tritium leak from laboratory walls to the environment and residual tritium amounts in concrete are estimated based on previous data. Three cases of accidental or chronic tritium release to laboratory air are discussed using the diffusion-adsorption model.


Development of advanced neutron multipliers for DEMO blankets

中道 勝; 金 宰煥

Fusion Science and Technology, 66, p.157 - 162, 2014/08

 被引用回数:1 パーセンタイル:87.59(Nuclear Science & Technology)

Advanced neutron multipliers and tritium breeders with higher stability at high temperature are desired. Beryllide is one of candidates for the advanced neutron multipliers. To fabricate the beryllide pebbles, a rotating electrode method (REM) was selected. Beryllide electrode fro the REM is necessary. Beryllide electrode has been successfully fabricated by the plasma sintering method. The prototypic beryllide pebbles were successfully fabricated by the REM using this plasma-sintered beryllide electrode. As a advanced tritium breeder, Li$$_{2}$$TiO$$_{3}$$ with excess Li (Li$$_{2+x}$$TiO$$_{3+y}$$) is one of the candidates. For raw material fabarication, synthesis process of Li$$_{2+x}$$TiO$$_{3+y}$$ powder has been developed by the solid phase reaction. From the granulation result by the emulsion method using this raw material, the prototypic pebbles of the Li$$_{2+x}$$TiO$$_{3+y}$$ with less than 5$$mu$$m in grain size and high sphericity, were successfully fabricated.


Honeycomb Palladium catalyst for the oxidation of tritiated hydrocarbons produced in tritium facilities

岩井 保則; 佐藤 克美; 山西 敏彦

Fusion Science and Technology, 66(1), p.214 - 220, 2014/07

 被引用回数:4 パーセンタイル:57.92(Nuclear Science & Technology)

トリチウム化炭化水素の酸化プロセスに適用できるハニカム型パラジウム触媒を開発した。本研究ではパラジウム担持密度が反応速度に与える影響を精査するため2, 5, 10g/Lの三種類のパラジウム密度を持つ触媒を準備した。本研究では炭化水素としてトリチウム化メタンを使用した。ハニカム型パラジウム触媒におけるトリチウム化メタン酸化の総括反応速度係数を空間速度1000から6300h$$^{-1}$$、メタン濃度0.004から100ppm,触媒温度322から673Kの範囲で流通式反応器を用いて評価した。触媒のパラジウム担持密度がトリチウム化メタン酸化の反応速度に与える影響はわずかであった。試験した空間速度の範囲では総括反応速度係数は空間速度に比例した。総括反応速度係数はメタン濃度が10ppm以下ではメタン濃度に依存しなかった。


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:57.92(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.


Neutronics of SiC-LiPb high temperature blanket for tritium production

Kwon, S.*; 佐藤 聡; 笠田 竜太*; 小西 哲之*

Fusion Science and Technology, 64(3), p.599 - 603, 2013/09

 被引用回数:2 パーセンタイル:76.57(Nuclear Science & Technology)


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