※ 半角英数字
 年 ~ 
検索結果: 111 件中 1件目~20件目を表示


Initialising ...



Initialising ...


Initialising ...


Initialising ...


Initialising ...


Initialising ...


Initialising ...


Initialising ...



Evaluation of residual stress relaxation in a rolled joint by neutron diffraction

林 眞琴*; Root, J. H.*; Rogge, R. B.*; 徐 平光

Quantum Beam Science (Internet), 2(4), p.21_1 - 21_16, 2018/12

The rolled joint of pressure tube, consisting of three axial symmetric parts, modified SUS403 stainless steel, Zr-2.5Nb pressure tube and Inconel-718, has been examined by neutron diffraction for residual stresses. It was heat treated at 350$$^{circ}$$C for 30, 130 and 635 hours to simulate the thermal aging of the rolled joint over the lifetime of the advanced thermal reactor at 288$$^{circ}$$C for 1, 5 and 30 years. The crystal lattice strains at various locations in the rolled joint before and after the aging treatments were measured by neutron diffraction and the residual stress distribution in the rolled joint was evaluated by using the Kroner elastic model and the generalized Hooke's law. In the crimp region of the rolled joint, it was found that the aging treatment had weak effect on the residual stresses in the Inconel and the SUS403. In the non-aged Zr-2.5Nb, the highest residual stresses were found near its interface with the SUS430. In the Zr-2.5Nb in the crimp region near its interface with the SUS430, the average compressive axial stress was -440 MPa, having no evident change during the long-time aging. In the Zr-2.5Nb outside closest to the crimp region, the tensile axial and hoop stresses were relieved during the 30 hours aging. The hoop stresses in the crimp region evolved from an average tensile stress of 80 MPa to an average compressive stress of 230 MPa after the 635 hours aging, suggesting that the rolled joint had a good long-term sealing ability against the leakage of high temperature water.


Temperature of thermal spikes induced by swift heavy ions

松崎 勝太*; 林 宏明*; 中嶋 薫*; 松田 誠; 左高 正雄*; 辻本 将彦*; Toulemonde, M.*; 木村 健二*

Nuclear Instruments and Methods in Physics Research B, 406(Part B), p.456 - 459, 2017/09

Few-nm sized gold, platinum and palladium nanoparticles were deposited on amorphous silicon nitride films. These films were irradiated with 420 MeV Au and 100 MeV Xe ions. Temperature distributions of thermal spikes produced by these ions were evaluated by observing desorption of the nanoparticles from the target surfaces upon ion impact. It was found that the temperature of the thermal spike produced by 420 MeV Au is higher than 100 MeV Xe. The observed temperature of the thermal spike at the entrance surface is slightly lower than that at the exit surface both for 420 MeV Au and 100 MeV Xe ions. These results can be well explained by the inelastic thermal spike model.


Rapid measurement scheme for texture in cubic metallic materials using time-of-flight neutron diffraction at iMATERIA

小貫 祐介*; 星川 晃範*; 佐藤 成男*; 徐 平光; 石垣 徹*; 齋藤 洋一*; 轟 秀和*; 林 眞琴*

Journal of Applied Crystallography, 49(5), p.1579 - 1584, 2016/10


 被引用回数:7 パーセンタイル:26(Chemistry, Multidisciplinary)

The authors have developed texture measurement system on a time-of flight neutron diffractometer, iMATERIA (BL20, MLF/J-PARC, Japan). Quantitative Rietveld texture analysis for a duplex stainless steel was possible with one neutron beam exposure for several minutes without sample rotation. The minimum number of diffraction spectra required for the Rietveld texture analysis was experimentally determined as $$sim$$100. The suggested rapid measurement scheme used 132 spectra and determined volume fractions of texture components in both ferrite and austenite phases, quantitatively. This quantitative and rapid measurement scheme was established by utilizing the features of iMATERIA as a powder diffractometer, i.e. fairly high resolution in d-spacing and numerous detectors equipped in a wide range of scattering angle.


Deuterium permeation behavior for damaged tungsten by ion implantation

大矢 恭久*; Li, X.*; 佐藤 美咲*; 湯山 健太*; 小柳津 誠; 林 巧; 山西 敏彦; 奥野 健二*

Journal of Nuclear Science and Technology, 53(3), p.402 - 405, 2016/03

 被引用回数:5 パーセンタイル:23.48(Nuclear Science & Technology)



R&D activities of tritium technologies on Broader Approach in Phase 2-2

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

Fusion Engineering and Design, 98-99, p.1792 - 1795, 2015/10

 パーセンタイル:100(Nuclear Science & Technology)



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:66.76(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

 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.


Study of safety features and accident scenarios in a fusion DEMO reactor

中村 誠; 飛田 健次; Gulden, W.*; 渡邊 和仁*; 染谷 洋二; 谷川 尚; 坂本 宜照; 荒木 隆夫*; 松宮 壽人*; 石井 響子*; et al.

Fusion Engineering and Design, 89(9-10), p.2028 - 2032, 2014/10

 被引用回数:8 パーセンタイル:25.95(Nuclear Science & Technology)



Hydrogen isotope behavior on a water-metal boundary with simultaneous transfer from and to the metal surface

林 巧; 磯部 兼嗣; 中村 博文; 小林 和容; 大矢 恭久*; 奥野 健二*; 小柳津 誠; 枝尾 祐希; 山西 敏彦

Fusion Engineering and Design, 89(7-8), p.1520 - 1523, 2014/10

 パーセンタイル:100(Nuclear Science & Technology)

トリチウムの閉じ込めは核融合炉の最も重要な安全上の課題である。特に、水冷却のトリチウム増殖ブランケットではトリチウムの冷却水への移行が重要である。そのため、1kPaの純トリチウムを封入した金属試料配管(純鉄や7ミクロン程度の金メッキを施した純鉄)を高温高圧水容器(150$$^{circ}$$C, 0.8MPa)にいれ、金属側から水中及び水蒸気中に移行するトリチウムを化学形別に測定した。また、高温高圧重水(300$$^{circ}$$C, 15MPa)からの各種金属配管(純鉄,純ニッケル,ステンレス鋼(SS304),金メッキ純鉄など)への重水素の移行挙動を調べ、水側から金属側への移行を確認した。今回、上記の同時移行挙動を、重水からの重水素の安定移行確認後に軽水素を試料配管内側へ導入することにより、検証した。


Key aspects of the safety study of a water-cooled fusion DEMO reactor

中村 誠; 飛田 健次; 染谷 洋二; 谷川 尚; Gulden, W.*; 坂本 宜照; 荒木 隆夫*; 渡邊 和仁*; 松宮 壽人*; 石井 響子*; et al.

Plasma and Fusion Research (Internet), 9, p.1405139_1 - 1405139_11, 2014/10




徐 平光; 星川 晃範*; 林 真琴*; 秋田 貢一; 森井 幸生*; 石垣 徹*

日本材料学会第48回X線材料強度に関するシンポジウム講演論文集, p.7 - 9, 2014/07

Time-of-flight neutron diffraction may evidently accelerate the bulk texture measurement speed through the proper combination of multiple orientations distributed neutron detectors and the simultaneous multiple diffraction peak acquisition, and only few sample rotations are needed to be carried out. In addition to the omega-axis rotatable sample changer, a dedicated omega/chi two-axis rotatable goniometer is under urgent development. It is highly expected to play an important role to evaluate the bulk texture evolution of advanced materials during thermomechanical controlling process. Though the intrinsic difference in neutron diffraction spectra from different orientations (determined by each set of Bragg angle/azimuthal angle) evidently increases the technical difficulty in rapid texture analysis, the development of Materials Analysis Using Diffraction (MAUD, developed by Luca Lutterotti, et al.) and other relevant software/programs are bringing us much convenience. Moreover, in order to increase the accessibility to neutron diffraction bulk texture measurement instruments, the various cooperative researches and the mail-in services are being planned.



柳澤 孝一; 林 俊夫*; 生沼 優*; 竹森 基*; 石川 貴則*; 岡谷 智一*; 西垣 誠*

社団法人物理探査学会第129回(平成25年度秋季)学術講演会講演論文集, p.287 - 288, 2013/10



Overview of R&D activities on tritium processing and handling technology in JAEA

山西 敏彦; 中村 博文; 河村 繕範; 岩井 保則; 磯部 兼嗣; 小柳津 誠; 山田 正行; 鈴木 卓美; 林 巧

Fusion Engineering and Design, 87(5-6), p.890 - 895, 2012/08

 被引用回数:1 パーセンタイル:85.4(Nuclear Science & Technology)



Hydrogen isotope permeation from cooling water through various metal piping

林 巧; 中村 博文; 磯部 兼嗣; 小林 和容; 小柳津 誠; 山西 敏彦; 大矢 恭久*; 奥野 健二*

Fusion Engineering and Design, 87(7-8), p.1333 - 1337, 2012/08

 被引用回数:6 パーセンタイル:42.4(Nuclear Science & Technology)



Design study and comparative evaluation of JSFR failed fuel detection system

相澤 康介; 近澤 佳隆; 石川 信行; 久保 重信; 岡崎 仁*; 水戸 誠*; 戸澤 克弘*; 林 真照*

Proceedings of 2012 International Congress on Advances in Nuclear Power Plants (ICAPP '12) (CD-ROM), p.465 - 474, 2012/06



Effects of tritiated water on corrosion behavior of SUS304

小柳津 誠; 磯部 兼嗣; 林 巧; 山西 敏彦

Fusion Science and Technology, 60(4), p.1515 - 1518, 2011/11

 被引用回数:3 パーセンタイル:66.23(Nuclear Science & Technology)

SUS304ステンレス鋼の腐食挙動に及ぼすトリチウム水の影響に関し、電気化学手法の一つであるターフェル外挿法を用いて算出される腐食電位と腐食速度を用いて解明を試みた。トリチウム濃度,溶存酸素濃度、そしてpHをパラメータとして実験を行った結果、ある一定の条件下においてはトリチウムによる腐食速度増加が観測された。また、トリチウム水による腐食への影響には2種類以上の機構が存在した。一つは自己不動態化阻害による腐食速度の増加であり、高腐食条件下では1 N H$$_{2}$$SO$$_{4}$$電解質中にて観測された。それ以外の影響は溶存酸素とトリチウム濃度に依存しており、1 N H$$_{2}$$SO$$_{4}$$だけでなく、1 N Na$$_{2}$$SO$$_{4}$$中においても観測された。


Permeation behavior of tritium through F82H steel

小柳津 誠; 磯部 兼嗣; 中村 博文; 林 巧; 山西 敏彦

Journal of Nuclear Materials, 417(1-3), p.1143 - 1146, 2011/10

 被引用回数:4 パーセンタイル:57.93(Materials Science, Multidisciplinary)



Hydrogen isotope behavior transferring through water metal boundary

林 巧; 中村 博文; 磯部 兼嗣; 小林 和容; 小柳津 誠; 大矢 恭久*; 奥野 健二*; 山西 敏彦

Fusion Science and Technology, 60(1), p.369 - 372, 2011/07

 被引用回数:2 パーセンタイル:75.97(Nuclear Science & Technology)

Tritium confinement is the most important safety issue in the fusion reactor. Specially, tritium behavior transferring through water metal boundary is very important to design tritium plant with breading blanket system using cooling water. A series of tritium permeation experiment into pressurized water jacket with He or jacket purging less than 1000 ppm of water vapor in Ar has been performed through pure iron piping, which contained about 1 kPa of pure tritium gas at 423 K, with monitoring the chemical forms of tritium permeated into water or water vapor jackets. The effect of metal surface condition was also investigated, such as oxidation to magnetite or gold plating on pure iron. The results clearly show that chemical species of permeated tritium depends on the oxygen population on the metal boundary. In case of pure iron, several hundreds ppm of H$$_{2}$$O is enough to transfer tritium as HTO from the boundary surface to outer jacket. When oxygen population on the boundary surface decreases by gold plating, HT fraction increases drastically. On the other hand, it is also found the possibility of hydrogen generation effect on the metal boundary, such as Schikorr reaction. In order to discuss more detail mechanism, actual hydrogen transfer behavior from water to metal was investigated as a function of temperature.


Dynamic behaviors of deuterium retained in SS-316 oxidized at various temperatures

小林 誠*; Wang, W.*; 倉田 理江; 松山 政夫*; 林 巧; 山西 敏彦; 朝倉 大和*; 大矢 恭久*; 奥野 健二*

Fusion Science and Technology, 60(1), p.403 - 406, 2011/07

 パーセンタイル:100(Nuclear Science & Technology)



Effect of tritium and dissolved oxygen on anodic polarization of SUS304 stainless steel in sulfuric acid solution

小柳津 誠; 磯部 兼嗣; 林 巧; 山西 敏彦

Journal of Nuclear Science and Technology, 48(6), p.880 - 884, 2011/06

Since exotic corrosion of stainless steels in tritiated water can be expected, anodic polarization of SUS304 stainless steel sample in approximately 5wt.% sulfuric acid solution were performed at various concentrations of tritium and dissolved oxygen (hereafter DO) in the electrolyte. The inhibitory effect of tritium on the passivation could be observed with DO even at a tritium concentration electrolyte as low as 2.2 kBq cm$$^{-3}$$. This effect became more pronounced as the tritium concentration increased. It was suggested that the inhibitory reaction depending on tritium concentration would compete with the self-passivation depending on DO concentration (hereafter [DO]), since there was found to be a threshold [DO] for self-passivation at each tritium concentration.

111 件中 1件目~20件目を表示