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Yamanaka, Kenta*; Kuroda, Asumi*; Ito, Miyu*; Mori, Manami*; Bian, H.*; Shobu, Takahisa; Sato, Shigeo*; Chiba, Akihiko*
Additive Manufacturing, 37, p.101678_1 - 101678_12, 2021/01
Times Cited Count:18 Percentile:87.78(Engineering, Manufacturing)Mori, Manami*; Yamanaka, Kenta*; Sato, Shigeo*; Tsubaki, Shinki*; Sato, Kozue*; Kumagai, Masayoshi*; Imafuku, Muneyuki*; Shobu, Takahisa; Chiba, Akihiko*
Journal of the Mechanical Behavior of Biomedical Materials, 90, p.523 - 529, 2019/02
Times Cited Count:17 Percentile:70.17(Engineering, Biomedical)Hatano, Masaharu*; Kubota, Yoshiki*; Shobu, Takahisa; Mori, Shigeo*
Philosophical Magazine Letters, 96(6), p.220 - 227, 2016/06
Times Cited Count:7 Percentile:35.68(Materials Science, Multidisciplinary)We have investigated the formation process of '-martensite from the -phase induced by external strain using synchrotron diffraction experiments, combined with Lorentz transmission electron microscopy (TEM) and high-resolution TEM observations. It is clearly demonstrated that -martensite with hexagonal symmetry appears as an intermediate structure during the plastic deformation of SUS304 stainless steel. In addition to stacking faults and dislocations, interfaces between the twin structures presumably play a key role in the formation of -martensite.
Masaki, Kiyotaka*; Kameshima, Yohei*; Hisamori, Noriyuki*; Sano, Yuji*; Akita, Koichi; Shobu, Takahisa
Zairyo, 62(5), p.297 - 304, 2013/05
Effects of laser peening without protective coating (LPwC) for high cycle fatigue property on + type Ti-6Al-4V alloy were investigated. As the results of peening effect investigation, it was clear that the surface layer was slightly hardened and high level compressive residual stress was induced near the surface by the LPwC treatment. However, the fatigue property was not improved by the LPwC treatment on the condition. One of the reasons was thought notch effects by surface roughness, then fatigue tests with surface polished LPwC specimen were carried out. However, the fatigue life of polished LPwC specimen was shorter than that of LPwC specimen unexpectedly.
Jo, Takahisa; Goto, Takehiro; Yabuki, Kentaro; Ikegami, Kazunori; Miyagawa, Takayuki; Mori, Tetsuya; Kubo, Atsuhiko; Kitano, Akihiro; Nakagawa, Hiroki; Kawamura, Yoshiaki; et al.
JAEA-Technology 2010-052, 84 Pages, 2011/03
The prototype fast breeder reactor MONJU resumed the System Startup Test (SST) on May 6th 2010 after five months and fourteen years shutdown since the sodium leakage of the secondary heat transport system on December 1995. Core Confirmation Test (CCT) is the first step of SST, which consists of three steps. CCT was finished on July 22nd after 78 days tests. CCT is composed 20 test items including control rods' worth evaluation, radiation dose measurement etc..
Takase, Kazuyuki; Shobu, Takahisa; Tsukimori, Kazuyuki; Muramatsu, Toshiharu
Proceedings of 2010 International Congress on Advances in Nuclear Power Plants (ICAPP '10) (CD-ROM), p.1725 - 1732, 2010/06
At the commercial use stage in sodium-cooled fast breeder reactors, securing maintenance and repair better than an equal to that of present water-cooled reactors is needed. Especially a repair technology that secures the plant integrity for long-term operation period becomes indispensable in the heat exchanger tubes of the steam generator that form the boundary of sodium and water coolants. Then the present study focused on the standardization of welding technology with a laser. An experimental study regarding the welding of a stainless steel plate with the laser using fine metal powders is being performed. Moreover, a numerical study is performed to simulate the welding of the fine metal powder on the stainless steel plate. The fine metal powder is made of iron, and is heated by the laser beam, and then melts exceeding the melting temperature. This paper reports the computational results of the welding phenomenon of some metal powders which changes from solid to liquid and liquid to solid. The results were compared with the experimental results qualitatively. It was concluded that a welding simulation is possible and the present numerical approach will be effective.
Takase, Kazuyuki; Muramatsu, Toshiharu; Shobu, Takahisa; Tsukimori, Kazuyuki
Proceedings of 2009 ASME International Mechanical Engineering Congress & Exposition (IMECE 2009) (CD-ROM), 2 Pages, 2009/11
no abstracts in English
Takase, Kazuyuki; Shobu, Takahisa; Tsukimori, Kazuyuki; Muramatsu, Toshiharu
Kashika Joho Gakkai-Shi, 29(Suppl.2), p.113 - 114, 2009/10
no abstracts in English
Tobita, Kenji; Nishio, Satoshi; Enoeda, Mikio; Kawashima, Hisato; Kurita, Genichi; Tanigawa, Hiroyasu; Nakamura, Hirofumi; Honda, Mitsuru; Saito, Ai*; Sato, Satoshi; et al.
Nuclear Fusion, 49(7), p.075029_1 - 075029_10, 2009/07
Times Cited Count:135 Percentile:97.73(Physics, Fluids & Plasmas)Recent design study on SlimCS focused mainly on the torus configuration including blanket, divertor, materials and maintenance scheme. For vertical stability of elongated plasma and high beta access, a sector-wide conducting shell is arranged in between replaceable and permanent blanket. The reactor adopts pressurized-water-cooled solid breeding blanket. Compared with the previous advanced concept with supercritical water, the design options satisfying tritium self-sufficiency are relatively scarce. Considered divertor technology and materials, an allowable heat load to the divertor plate should be 8 MW/m or lower, which can be a critical constraint for determining a handling power of DEMO (a combination of alpha heating power and external input power for current drive).
Shimizu, Nobuaki*; Oue, Atsushi*; Otsuki, Takahiro*; Mori, Takahisa*; Yamaguchi, Kayo*; Nakamura, Takako*; Wada, Seiichi*; Kobayashi, Yasuhiko; Hoshino, Hiroo*
JAEA-Review 2006-042, JAEA Takasaki Annual Report 2005, P. 105, 2007/02
Asakura, Nobuyuki; Kato, Takako*; Nakano, Tomohide; Takamura, Shuichi*; Tanabe, Tetsuo*; Iio, Shunji*; Nakajima, Noriyoshi*; Ono, Yasushi*; Ozeki, Takahisa; Takechi, Manabu; et al.
Purazuma, Kaku Yugo Gakkai-Shi, 82(7), p.448 - 450, 2006/07
no abstracts in English
Ito, Keisuke; Kawahara, Hirotaka; Mori, Takero; Jo, Takahisa; Ariyoshi, Masahiko; Isozaki, Kazunori
JNC TN9410 2005-008, 267 Pages, 2005/03
Control characteristic tests of reactor coolant temperature control system were carried out to confirm its controlling constant to make MK-III hear transport system control stably, and stability against actual disturbance to the plant. The control characteristic test consists of three kinds of tests. As a result, the optimum PI parameters of the reactor coolant temperature control system was confirmed that the proportional gain is between from 0.36 to 1.12(approximately half of MK-II), the integral time is 80 respectively. The gain margin of the control system was between from 7 to 19dB of through the vane opening range.
Kawano, Yasunori; Kawahata, Kazuo*; Kusama, Yoshinori; Sasao, Mamiko*; Sugie, Tatsuo; Mase, Atsushi*; Asakura, Nobuyuki; Kato, Takako*; Takamura, Shuichi*; Tanabe, Tetsuo*; et al.
Purazuma, Kaku Yugo Gakkai-Shi, 81(2), p.128 - 130, 2005/02
no abstracts in English
Iwata, Koji; Tsukimori, Kazuyuki; Chiba, Takahisa*; Sakai, Shinkichi*; Uenom, M.*; Sakai, Tetsuya*; Sakai, Hikaru*
JNC TN9520 2003-006, 569 Pages, 2003/09
FINAS is a general purpose structural analysis computer program developed by Japan Nuclear Cycle Development Institute for the calculation of static, dynamic and thermal responses of elastic and inelastic structures by the finite element method. This document contains typical analysis examples that illustrate applications of FINAS to a number of structural engineering problems. The first part of this document presents fundamental examples in which numerical solutions by FINAS are compared with some analytical reference solutions, and the second part of this document presents more complex examples intended for practical application. All of the input data image and principal results for each problem are included in this document for beginners convenience. All the analyses are performed using the Version 13.0 of FINAS
Kamada, Yutaka; Fujita, Takaaki; Ishida, Shinichi; Kikuchi, Mitsuru; Ide, Shunsuke; Takizuka, Tomonori; Shirai, Hiroshi; Koide, Yoshihiko; Fukuda, Takeshi; Hosogane, Nobuyuki; et al.
Fusion Science and Technology (JT-60 Special Issue), 42(2-3), p.185 - 254, 2002/09
Times Cited Count:33 Percentile:48.48(Nuclear Science & Technology)With the main aim of providing physics basis for ITER and the steady-state tokamak reactors, JT-60/JT-60U has been developing and optimizing the operational concepts, and extending the discharge regimes toward sustainment of high integrated performance in the reactor relevant parameter regime. In addition to achievement of the equivalent break-even condition (QDTeq up to 1.25) and a high fusion triple product = 1.5E21 m-3skeV, JT-60U has demonstrated the integrated performance of high confinement, high beta-N, full non-inductive current drive with a large fraction of bootstrap current in the reversed magnetic shear and in the high-beta-p ELMy H mode plasmas characterized by both internal and edge transport barriers. The key factors in optimizing these plasmas are profile and shape controls. As represented by discovery of various Internal Transport Barriers, JT-60/JT-60U has been emphasizing freedom and restriction of profiles in various confinement modes. JT-60U has demonstrated applicability of these high confinement modes to ITER and also clarified remaining issues.
Nagashima, Keisuke; Kikuchi, Mitsuru; Kurita, Genichi; Ozeki, Takahisa; Aoyagi, Tetsuo; Ushigusa, Kenkichi; Neyatani, Yuzuru; Kubo, Hirotaka; Mori, Kensuke*; Nakagawa, Shoji*; et al.
Fusion Engineering and Design, 36(2-3), p.325 - 342, 1997/05
Times Cited Count:1 Percentile:14.48(Nuclear Science & Technology)no abstracts in English
Nagashima, Keisuke; Kikuchi, Mitsuru; ; Ozeki, Takahisa; Aoyagi, Tetsuo; Ushigusa, Kenkichi; Neyatani, Yuzuru; Kubo, Hirotaka; Mori, Katsuharu*; *; et al.
Fusion Engineering and Design, 36(2-3), p.325 - 342, 1997/00
no abstracts in English
Koide, Yoshihiko; Takizuka, Tomonori; Takeji, Satoru; Ishida, Shinichi; Kikuchi, Mitsuru; Kamada, Yutaka; Ozeki, Takahisa; Neyatani, Yuzuru; Shirai, Hiroshi; Mori, Masahiro; et al.
Plasma Physics and Controlled Fusion, 38(7), p.1011 - 1022, 1996/07
Times Cited Count:62 Percentile:85.39(Physics, Fluids & Plasmas)no abstracts in English
Kamada, Yutaka; Ushigusa, Kenkichi; Neyatani, Yuzuru; Naito, Osamu; Ozeki, Takahisa; Kawano, Yasunori; Yoshino, Ryuji; Kubo, Hirotaka; Fujita, Takaaki; Ishida, Shinichi; et al.
IAEA-CN-60/A5-5, 0, p.651 - 661, 1995/00
no abstracts in English
Kamada, Yutaka; Ushigusa, Kenkichi; Naito, Osamu; Neyatani, Yuzuru; Ozeki, Takahisa; Tobita, Kenji; Ishida, Shinichi; Yoshino, Ryuji; Kikuchi, Mitsuru; Mori, Masahiro; et al.
Nuclear Fusion, 34(12), p.1605 - 1618, 1994/00
Times Cited Count:47 Percentile:79.78(Physics, Fluids & Plasmas)no abstracts in English