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Journal Articles

Quantifying the dislocation structures of additively manufactured Ti-6Al-4V alloys using X-ray diffraction line profile analysis

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)

Journal Articles

Tuning strain-induced $$gamma$$-to-$$varepsilon$$ martensitic transformation of biomedical Co-Cr-Mo alloys by introducing parent phase lattice defects

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)

Journal Articles

Presence of $$varepsilon$$-martensite as an intermediate phase during the strain-induced transformation of SUS304 stainless steel

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 $$alpha$$'-martensite from the $$gamma$$-phase induced by external strain using ${it in situ}$ synchrotron diffraction experiments, combined with Lorentz transmission electron microscopy (TEM) and high-resolution TEM observations. It is clearly demonstrated that $$varepsilon$$-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 $$varepsilon$$-martensite.

Journal Articles

Effects of laser peening on rotating bending fatigue properties of Ti-6Al-4V titanium alloy

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 $$alpha$$+$$beta$$ 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.

JAEA Reports

Core confirmation test in system startup test of the fast breeder reactor MONJU

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

JAEA-Technology-2010-052.pdf:17.14MB

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..

Journal Articles

Numerical investigation on melting characteristics of minuteness metal powders by laser welding

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.

Journal Articles

Computational simulations on melting process of fine metal powders with laser irradiation welding

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

Journal Articles

On quantitative estimation of laser melting phenomenon with numerical visualization technique

Takase, Kazuyuki; Shobu, Takahisa; Tsukimori, Kazuyuki; Muramatsu, Toshiharu

Kashika Joho Gakkai-Shi, 29(Suppl.2), p.113 - 114, 2009/10

no abstracts in English

Journal Articles

Compact DEMO, SlimCS; Design progress and issues

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$$^{2}$$ 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).

Journal Articles

Effects of heavy-ion, UV-C, and X-ray irradiation on the susceptibilities of human cells to HIV-1 infection

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

Journal Articles

Report of ITPA (International Tokamak Physics Activity) meetings, 17

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

JAEA Reports

MK-III Performance Tests in JOYO; Control Characteristic Tests of Reactor Coolant Temperature Control System

Ito, Keisuke; Kawahara, Hirotaka; Mori, Takero; Jo, Takahisa; Ariyoshi, Masahiko; Isozaki, Kazunori

JNC TN9410 2005-008, 267 Pages, 2005/03

JNC-TN9410-2005-008.pdf:108.4MB

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.

Journal Articles

Report of ITPA (International Tokamak Physics Activity) meeting, 13

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

JAEA Reports

FINAS Example Manual (Second Edition)

Iwata, Koji; Tsukimori, Kazuyuki; Chiba, Takahisa*; Sakai, Shinkichi*; Uenom, M.*; Sakai, Tetsuya*; Sakai, Hikaru*

JNC TN9520 2003-006, 569 Pages, 2003/09

JNC-TN9520-2003-006.pdf:9.55MB

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

Journal Articles

Fusion plasma performance and confinement studies on JT-60 and JT-60U

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.

Journal Articles

Physical design of JT-60 Super Upgrade

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

Journal Articles

Physical design of JT-60 super upgrade

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

Journal Articles

Internal transport barrier with improved confinement in the JT-60U tokamak

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

Journal Articles

Steady state high performance in JT-60U

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

Journal Articles

Non-inductively current driven H mode with high-$$beta$$$$_{N}$$ and high-$$beta$$$$_{P}$$ values in JT-60U

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

33 (Records 1-20 displayed on this page)