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Characterization and corrosion behavior of Al-added high Mn ODS austenitic steels in oxygen-saturated lead-bismuth eutectic

Haoran, W.*; Yu, H.*; Liu, J.*; 近藤 創介*; 大久保 成彰; 笠田 竜太*

Corrosion Science, 209, p.110818_1 - 110818_12, 2022/12

 被引用回数:1 パーセンタイル:44.11(Materials Science, Multidisciplinary)



Corrosion behaviour of Al-added high Mn austenitic steels in molten lead bismuth eutectic with saturated and low oxygen concentrations at 450$$^{circ}$$C

Wang, H.*; Yu, H.*; 近藤 創介*; 大久保 成彰; 笠田 竜太*

Corrosion Science, 175, p.108864_1 - 108864_12, 2020/10

 被引用回数:16 パーセンタイル:79.8(Materials Science, Multidisciplinary)



Structure near the $$K^- + p + p$$ threshold in the in-flight $$^3$$He$$(K^-,Lambda p)n$$ reaction

佐田 優太*; 谷田 聖; J-PARC E15 Collaboration*; 他69名*

Progress of Theoretical and Experimental Physics (Internet), 2016(5), p.051D01_1 - 051D01_11, 2016/05


 被引用回数:49 パーセンタイル:90.11(Physics, Multidisciplinary)

To search for an $$S = -1$$ di-baryonic state which decays to $$Lambda p$$, the $$^3$$He$$(K^-,Lambda p)n_{rm missing}$$ reaction was studied at 1.0 GeV/$$c$$. Unobserved neutrons were kinematically identified from the missing mass $$M_X$$ of the $$^3$$He$$(K^-, Lambda p)X$$ reaction in order to have a large acceptance for the $$Lambda pn$$ final state. The observed $$Lambda pn$$ events, distributed widely over the kinematically allowed region of the Dalitz plot, establish that the major component comes from a three-nucleon absorption process. A concentration of events at a specific neutron kinetic energy was observed in a region of low momentum transfer to the $$Lambda p$$. To account for the observed peak structure, the simplest $$S$$-wave pole was assumed to exist in the reaction channel, having a Breit-Wigner form in energy and with a Gaussian form factor. A minimum $$chi^2$$ method was applied to deduce its mass, $$M_X = 2355^{+6}_{-8}({rm stat.}) pm 12({rm syst.})$$ MeV/$$c^2$$, and decay width, $$Gamma_X = 110^{+19}_{-17}({rm stat.}) pm 27({rm syst.})$$ MeV/$$c^2$$, respectively. The form factor parameter $$Q_X sim 400$$ MeV/$$c$$ implies that the range of the interaction is about 0.5 fm.


Corrosion behavior of F82H exposed to high temperature pressurized water with a rotating apparatus

金井 亮彦*; 笠田 竜太*; 中島 基樹; 廣瀬 貴規; 谷川 尚; 榎枝 幹男; 小西 哲之*

Journal of Nuclear Materials, 455(1-3), p.431 - 435, 2014/12

 被引用回数:0 パーセンタイル:0.01(Materials Science, Multidisciplinary)

The present study reports the compatibility of a reduced-activation ferritic steel F82H exposed to high temperature pressurized water using a rotating disk apparatus at 573 K. Every rotated sample reduces their weight due to water flow. Cross-sectional observations revealed that difference of apparent rotating speed on the microstructural change is limited.


Compatibility of Ni and F82H with liquid Pb-Li under rotating flow

金井 亮彦*; Park, C.*; 登尾 一幸*; 笠田 竜太*; 小西 哲之*; 廣瀬 貴規; 野澤 貴史; 谷川 博康

Fusion Engineering and Design, 89(7-8), p.1653 - 1657, 2014/10

 被引用回数:4 パーセンタイル:32.74(Nuclear Science & Technology)

The present study reports the compatibility of a reduced-activation ferritic steel F82H and Ni exposed to liquid Pb-Li flow using a rotating disk apparatus at 873 K. Cross-sectional observations revealed that grain boundary attack of Pb caused a liquid metal embrittlement of Ni and formation of pitting holes and Cr-depleted zone in F82H.


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:11 パーセンタイル:66.19(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.


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:9 パーセンタイル:55.39(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.


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:19.48(Nuclear Science & Technology)




笠田 竜太*; 後藤 拓也*; 藤岡 慎介*; 日渡 良爾*; 大山 直幸; 谷川 博康; 宮澤 順一*; 核融合炉実用化若手検討会*

プラズマ・核融合学会誌, 89(4), p.193 - 198, 2013/04



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.


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:24 パーセンタイル:86.63(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.


Super ODS steels R&D for fuel cladding of next generation nuclear systems, 1; Introduction and alloy design

木村 晃彦*; 笠田 竜太*; 岩田 憲幸*; 岸本 弘立*; Zhang, C. H.*; Isselin, J.*; Dou, P.*; Lee, J. H.*; Muthukumar, N.*; 奥田 隆成*; et al.

Proceedings of 2009 International Congress on Advances in Nuclear Power Plants (ICAPP '09) (CD-ROM), p.9220_1 - 9220_8, 2009/05



Super ODS steels R&D for fuel cladding of next generation nuclear systems, 6; Corrosion behavior in SCPW

Lee, J. H.*; 木村 晃彦*; 笠田 竜太*; 岩田 憲幸*; 岸本 弘立*; Zhang, C. H.*; Isselin, J.*; Dou, P.*; Muthukumar, N.*; 奥田 隆成*; et al.

Proceedings of 2009 International Congress on Advances in Nuclear Power Plants (ICAPP '09) (CD-ROM), p.9223_1 - 9223_6, 2009/05



Super ODS steels R&D for fuel cladding of next generation nuclear systems, 5; Mechanical properties and microstructure

笠田 竜太*; Lee, S. G.*; Lee, J. H.*; 大村 高正*; Zhang, C. H.*; Dou, P.*; Isselin, J.*; 木村 晃彦*; 井上 賢紀; 鵜飼 重治*; et al.

Proceedings of 2009 International Congress on Advances in Nuclear Power Plants (ICAPP '09) (CD-ROM), p.9072_1 - 9072_5, 2009/05



Super ODS steels R&D for fuel cladding of next generation nuclear systems, 8; Ion irradiation effects at elevated temperatures

岸本 弘立*; 笠田 竜太*; 木村 晃彦*; 井上 賢紀; 奥田 隆成*; 阿部 冨士雄*; 大貫 惣明*; 藤澤 敏治*

Proceedings of 2009 International Congress on Advances in Nuclear Power Plants (ICAPP '09) (CD-ROM), p.9219_1 - 9219_8, 2009/05



Fusion materials development program in the Broader Approach activities

西谷 健夫; 谷川 博康; 實川 資朗; 野澤 貴史; 林 君夫; 山西 敏彦; 土谷 邦彦; M$"o$slang, A.*; Baluc, N.*; Pizzuto, A.*; et al.

Journal of Nuclear Materials, 386-388, p.405 - 410, 2009/04

 被引用回数:31 パーセンタイル:88.73(Materials Science, Multidisciplinary)



Technical issues of reduced activation ferritic/martensitic steels for fabrication of ITER test blanket modules

谷川 博康; 廣瀬 貴規; 芝 清之; 笠田 竜太*; 若井 栄一; 芹澤 久*; 川人 洋介*; 實川 資朗; 木村 晃彦*; 幸野 豊*; et al.

Fusion Engineering and Design, 83(10-12), p.1471 - 1476, 2008/12

 被引用回数:78 パーセンタイル:97.95(Nuclear Science & Technology)



Impact of N-isotope composition control of ferritic steel on classification of radioactive materials from fusion reactor

林 孝夫; 笠田 竜太*; 飛田 健次; 西尾 敏; 沢井 友次; 谷川 博康; 實川 資朗

Fusion Engineering and Design, 82(15-24), p.2850 - 2855, 2007/10

 被引用回数:2 パーセンタイル:19.07(Nuclear Science & Technology)

核融合炉における浅地埋設可能な低レベル放射性廃棄物(LLM)の割合を増やすためのフェライト鋼中の窒素同位体濃縮の効果を調べた。おもに窒素から生成される炭素14は放射性廃棄物をLLMに分類するうえで重要な核種の一つである。今回の計算ではF82H(フェライト鋼)中の窒素の量は200ppmとした。窒素15の濃度は天然存在比の0.37%から95%に変更した。この濃縮によりアウトボード側の第一壁領域に設置したF82H中の$$^{14}$$C濃度は7.8$$times$$10$$^{4}$$から3.2$$times$$10$$^{4}$$Bq/gに減少し、$$^{14}$$Cの日本におけるLLM分類基準である3.7$$times$$10$$^{4}$$Bq/gを下回ることがわかった。常設ブランケットにおいては95%$$^{15}$$Nを用いた場合の最大$$^{14}$$C濃度は1.0$$times$$10$$^{4}$$Bq/gであった。一方、インボード側の$$^{14}$$C濃度はアウトボード側より低く、$$^{14}$$C濃度についてはインボード及びアウトボード側に設置したすべてのブランケット中のF82Hが95% $$^{15}$$N濃縮によりLLMに分類できることがわかった。


Status and key issues of reduced activation martensitic steels as the structural materials of ITER test blanket module and beyond

谷川 博康; 芝 清之; 廣瀬 貴規; 笠田 竜太*; 若井 栄一; 實川 資朗; 木村 晃彦*; 香山 晃*

Proceedings of 21st IAEA Fusion Energy Conference (FEC 2006) (CD-ROM), 6 Pages, 2007/03



Gamow-Teller decay of the $$T=1$$ nucleus $$^{46}$$Cr

大西 健夫*; Gelberg, A.*; 櫻井 博儀*; 米田 健一郎*; 青井 考*; 今井 伸明*; 馬場 秀忠*; Von Brentano, P.*; 福田 直樹*; 市川 雄一*; et al.

Physical Review C, 72(2), p.024308_1 - 024308_7, 2005/08

 被引用回数:21 パーセンタイル:78.11(Physics, Nuclear)

$$^{46}$$Crのベータ崩壊を理化学研究所のサイクロトロン加速器を用いて初めて測定し、$$B(GT)$$値0.64$$pm$$0.20が得られた。この実験値を$$pf$$殻模型空間を仮定した殻模型計算と比較し、その相互作用依存性を調べた。KB3, FPD6, GXPF2相互作用はそれぞれ実験値を誤差棒の範囲内で説明することはできるが、これらの理論値は1.5倍ほどの開きがあり、どの相互作用が優れているかは今後の精密測定が待たれることとなった。この比較的大きなベータ崩壊確率は、準重陽子描像により定性的に議論可能であることがわかった。

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