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Development of methods for reprocessing and reuse of tritium breeder materials in broader approach activities

星野 毅

Journal of Nuclear Materials, 442(1-3), p.S425 - S428, 2013/11

 被引用回数:4 パーセンタイル:62.81(Materials Science, Multidisciplinary)



Preliminary characterization of plasma-sintered beryllides as advanced neutron multipliers

中道 勝; 金 宰煥; 宗像 健三*; 柴山 環樹*; 宮本 光貴*

Journal of Nuclear Materials, 442(1-3), p.S465 - S471, 2013/11

 被引用回数:6 パーセンタイル:46.51(Materials Science, Multidisciplinary)

Advanced neutron multipliers with low swelling and high stability at high temperature are desired for pebble bed blankets. Beryllium intermetallic compounds (beryllides) are the most promising advanced neutron multipliers. Development of advanced neutron multiplier has been started between Japan and the EU in the DEMO R&D of the International Fusion Energy Research Centre (IFERC) project as a part of the Broader Approach activities. The plasma sintering method has been selected as a new beryllides synthesis method. The plasma sintering results in starting powder particle surface activation that enhances sinterability and reduces high temperature exposure. The plasma sintering shows that the intermetallic compound beryllide such as Be$$_{12}$$Ti, Be$$_{17}$$Ti$$_{2}$$ and Be$$_{2}$$Ti can be directly synthesized from mixed elemental powders of Be and Ti at a temperature lower than the melting point. In this report, the preliminary characterization of plasma sintered Be-Ti beryllide was carried out such as reactivity with water vapor, microstructure analysis by ion irradiation effect and deuterium retention property compared with beryllium (Be) metal. From the result of the preliminary characterization, it revealed that plasma sintered Be-Ti beryllide sample has a good performance as a neutron multiplier. This beryllide sample has enough oxidation resistance, high radiation resistance and low deuterium retention property more than Be metal.


The Effect of sintering time on synthesis of plasma sintered beryllides

金 宰煥; 中道 勝

Journal of Nuclear Materials, 442(1-3), p.S461 - S464, 2013/11

 被引用回数:11 パーセンタイル:19.82(Materials Science, Multidisciplinary)

Development of advanced neutron multiplier has been started between Japan and EU in the DEMO R&D of the International Fusion Energy Research Centre (IFERC) project as a part of the Broader Approach activities. Plasma sintering method has been selected as a synthesis method for beryllides. The formation of Be$$_{12}$$Ti, Be$$_{17}$$Ti$$_{2}$$ and Be$$_{2}$$Ti intermetallics was identified in sintering at 1073-1273 K for 20 min under 50 MPa pressure, using starting mixed powder particles of Be and Ti. The elemental content of Be and Ti in the plasma sintered material decreased by consolidation enhancement with increasing sintering temperature, with only about 2% of the elemental phases remaining in 98% beryllides at 1273 K. This experiment shows that the intermetallic compound beryllides can be directly synthesized by the plasma sintering method at temperature which is lower than the melting point. Since beryllides as neutron multiplier are used at high temperature for a long time, it is considerably important to understand thermal properties of the beryllides. In this report, evaluation of thermal stability of plasma sintered Be-Ti beryllide was carried out.


Irradiation response in weldment and HIP joint of reduced activation ferritic/martensitic steel, F82H

廣瀬 貴規; Sokolov, M. A.*; 安堂 正己; 谷川 博康; 芝 清之; Stoller, R. E.*; Odette, G. R.*

Journal of Nuclear Materials, 442(1-3), p.S557 - S561, 2013/11

 被引用回数:5 パーセンタイル:46.51(Materials Science, Multidisciplinary)

The objective of this work is to investigate irradiation response in the joints of F82H. The joints of F82H were prepared using TIG welding, EB welding and Hot-Isostatic-Pressing (HIP). As for weld joints, mechanical specimens were cut out of weld-metal (WM), heat-affected-zone (HAZ). These specimens were irradiated in an instrumented irradiation capsule, RB-15J in HFIR at Oak Ridge National Laboratory. The irradiation temperature was controlled at 573 and 673 K using liquid lithium as a heating medium, and the irradiation dose was up to 6 dpa. Tensile tests after 573 K irradiation revealed that the hardening in WM and base metal (BM) are greater than 300 MPa. On the other hand, HAZ exhibits about half of that of the WM and BM. Since the HAZ is the weakest part in the joint even before irradiation, neutron irradiation significantly enhances the weakness of the HAZ and it could be in danger of local deformation at this region.


First-principles thermodynamic calculations of diffusion characteristics of impurities in $$gamma$$-iron

都留 智仁; 加治 芳行

Journal of Nuclear Materials, 442(1-3), p.S684 - S687, 2013/11

 被引用回数:3 パーセンタイル:62.81(Materials Science, Multidisciplinary)



An Atomistic modeling of He bubble stability at grain boundaries in alpha-Fe

鈴土 知明; 都留 智仁; 山口 正剛; 蕪木 英雄

Journal of Nuclear Materials, 442(1-3), p.S655 - S659, 2013/11

 被引用回数:5 パーセンタイル:46.51(Materials Science, Multidisciplinary)



Microsegregation in a F82H plate

酒瀬川 英雄; 谷川 博康

Journal of Nuclear Materials, 442(1-3), p.S18 - S22, 2013/11

 パーセンタイル:100(Materials Science, Multidisciplinary)



Application of master curve method to the evaluation of fracture toughness of F82H steels

Kim, B. J.; 笠田 竜太*; 木村 晃彦*; 若井 栄一; 谷川 博康

Journal of Nuclear Materials, 442(1-3), p.S38 - S42, 2013/11

 被引用回数:9 パーセンタイル:25.82(Materials Science, Multidisciplinary)

Fracture toughness data was obtained for the reduced-activation ferritic (RAF) steels F82H with different size of specimens (1 CT, half CT and quactor CT) using the master curve (MC) method in the transition temperature region. Effects of specimen size on the fracture toughness is not observed and the reference temperature ($$T$$$$_{0}$$) is around -108$$^{circ}$$C which has similar values to those (-119$$^{circ}$$C) of other previous works. However, the data are not well represented by a MC, showing a rather large number of data below the lower boundary curve. A new master curve was derived within the framework of the ASTM E1921 standard to apply the MC method to the F82H steel. New master curve analysis can be applicable to RAFS to estimate the reference temperature ($$T$$$$_{0}$$) with proper description of the data scatter in the transition temperature region of fracture toughness than that of the conventional master curve.


Effect of cation exchange on hydrogen adsorption property of mordenite for isotope separation

河村 繕範; 岩井 保則; 宗像 健三*; 山西 敏彦

Journal of Nuclear Materials, 442(1-3), p.S455 - S460, 2013/11

 被引用回数:7 パーセンタイル:34.56(Materials Science, Multidisciplinary)

ゼオライトは容易にカチオンを交換し、結果として簡単に細孔径を変化させることができる。カチオン交換したモルデナイトは77K以上の温度でも比較的良い同位体分離ができたと報告されている。しかし、吸着量,吸着速度,カチオンの種類,交換比率の関係はまだ明らかにされていない。本研究ではNa-MORを出発物質としてアルカリ金属,アルカリ土類金属イオンでカチオンを交換た試料を作り、77K, 159K, 175K及び195KでのH$$_{2}$$及びD$$_{2}$$の吸着量を測定した。Li-MOR及びCa-MORの吸着量は低圧域でNa-MORより大きくなった。逆にK-MORでは小さくなった。K-MORは明らかに細孔径が小さくなっていた。アルカリ金属イオンで交換した場合、原子番号が小さい方が吸着量は大きくなるのかもしれない。


Development of high-grade VPS-tungsten coatings on F82H reduced activation steel

徳永 知倫*; 渡辺 英雄*; 吉田 直亮*; 長坂 琢也*; 笠田 竜太*; Lee, Y.-J.*; 木村 晃彦*; 時谷 政行*; 光原 昌寿*; 檜木 達也*; et al.

Journal of Nuclear Materials, 442(1-3), p.S287 - S291, 2013/11

 被引用回数:5 パーセンタイル:46.51(Materials Science, Multidisciplinary)

VPS-W coating formed on F82H kept at about 873K in conventional plasma spray conditions has inhomogeneous texture; namely mixture of disarranged area composed of large re-solidified/un-melted grains, fine randomly oriented grains and pores, and well ordered area composed columnar grains. Heat load test indicate that elimination of the disarranged area is necessary to improve the heat load resistance of VPS-W. One can get W coating with texture of homogeneous columnar crystal grains by eliminating the re-solidified/un-melted large particles. Optimization of the W powder size was also effective to reduce number of randomly oriented fine grains and pores.


Mechanical properties of friction stir welded 11Cr-ferritic/martensitic steel

矢野 康英; 佐藤 裕*; 関尾 佳弘; 大塚 智史; 皆藤 威二; 小川 竜一郎; 粉川 博之*

Journal of Nuclear Materials, 442(1-3), p.S524 - S528, 2013/09

 被引用回数:8 パーセンタイル:34.56(Materials Science, Multidisciplinary)



Microstructure and high-temperature strength of high Cr ODS tempered martensitic steels

大塚 智史; 皆藤 威二; 丹野 敬嗣; 矢野 康英; 小山 真一; 田中 健哉

Journal of Nuclear Materials, 442(1-3), p.S89 - S94, 2013/09

 被引用回数:9 パーセンタイル:25.82(Materials Science, Multidisciplinary)

11-12CrODSマルテンサイト鋼の試作試験を実施した。試作材について、高温XRD, EPMA及び金相観察に基づくフェライト/マルテンサイト2相組織の定量評価を実施した。Crの増量による残留$$alpha$$フェライト相の過度な形成は、変態の駆動力評価に基づいて化学組成を調整することにより抑制できることがわかった。適度な残留$$alpha$$フェライトを含む11CrODSマルテンサイト鋼の製造に成功した。製造まま材の機械的特性評価を実施した結果、9Cr-ODS鋼と同等の高温クリープ強度を有していることがわかった。引張特性については、延性は9Cr-ODS鋼と同等であるが、0.2%耐力は低めとなった。


Engineering design of contact-type liquid level sensor for measuring thickness validation of liquid lithium jet in IFMIF/EVEDA lithium test loop

金村 卓治; 近藤 浩夫; 鈴木 幸子*; 帆足 英二*; 山岡 信夫*; 堀池 寛*; 古川 智弘; 井田 瑞穂; 中村 和幸; 松下 出*; et al.

Fusion Science and Technology, 62(1), p.258 - 264, 2012/07

 被引用回数:4 パーセンタイル:55.75(Nuclear Science & Technology)



Pd/ZrO$$_{2}$$ catalyst for the oxidation process of tritiated organic substances produced in fusion plants

岩井 保則; 佐藤 克美; 山西 敏彦

Fusion Science and Technology, 62(1), p.83 - 88, 2012/07

 被引用回数:3 パーセンタイル:64.33(Nuclear Science & Technology)



Overview of materials research and IFMIF-EVEDA under the Broader Approach framework

西谷 健夫; 谷川 博康; 山西 敏彦; Clement Lorenzo, S.*; Baluc, N.*; 林 君夫; 中島 徳嘉*; 木村 晴行; 杉本 昌義; Heidinger, R.*; et al.

Fusion Science and Technology, 62(1), p.210 - 218, 2012/07

 被引用回数:2 パーセンタイル:85.4(Nuclear Science & Technology)



IFMIF/EVEDA; Adjustment of scope and recent technical achievements

Garin, P.*; 杉本 昌義; IFMIF/EVEDA Integrated Project Team

Fusion Science and Technology, 62(1), p.219 - 225, 2012/07

 被引用回数:8 パーセンタイル:32.85(Nuclear Science & Technology)



Effects of carbon impurity on microstructural evolution in irradiated $$alpha$$-iron

阿部 陽介; 鈴土 知明; 實川 資朗; 都留 智仁; 塚田 隆

Fusion Science and Technology, 62(1), p.139 - 144, 2012/07

 被引用回数:5 パーセンタイル:48.35(Nuclear Science & Technology)



Adsorption behavior of hydrogen and deuterium on natural mordenite adsorbents at 77 K

宗像 健三*; 河村 繕範

Fusion Science and Technology, 62(1), p.71 - 76, 2012/07

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



Analysis of test matrix and design status of test modules of IFMIF

若井 栄一; 菊地 孝行; 横峯 健彦*; 山本 道好; Soldaini, M.*; Polato, A.*

Fusion Science and Technology, 62(1), p.246 - 251, 2012/07

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

In this paper, the test matrix of the IFMIF was evaluated. All test matrixes depend on the requirement of a database preparation schedule and the irradiation volume of irradiation modules such as high flux test module (HFTM), medium flux test module (MFTM) and low flux test module (LFTM), but the engineering design of HFTM is mainly proceeding. Accordingly, the lists of the experiments of small size specimens set in the HFTM to be performed in the PIE laboratories have been carefully analyzed. In the design of HFTM, two types of HFTM are proposed for RAFM steel irradiation by the EU KIT team and for the advanced materials by the JA team, and the difference was summarized.


Evaluation of creep properties of welded joint for reduced activation ferritic/martenstic steel

中田 隼矢; 谷川 博康; 木村 一弘*

no journal, , 

Since nuclear fusion reactors, except the DEMO reactor, are steadily operated, creep or creep fatigue is the main damage in blanket structure materials. Welding is mostly used for producing blanket modules, which use F82H as a structural material. This is because an early fracture occurs because of the Type IV damage, in which cracks occur during welding in the softening region of the heat-affected zone. This study evaluates microstructure for the F82H TIG and EB welded joints creep rupture materials, and discusses the evaluated the conditions for the occurrence of the Type IV damage.

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