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Plasma Science and technology 2009年第4期11卷 397-401页

作者： H.ZUSHI t.RYOUKAI K.KIKUKAWA t.morisaki R.BHAttACHARYAY t.YOSHINAGA K.HANADA t.SAKIMURA H.IDEI K.DONO N.NISHINO H.HONMA S.tASHIMA t.MUtOH S.KUBO K.NAGASAKI M.SAKAMOtO Y.NAKASHIMA Y.HIGASHIZONO K.N.SAtO K.NAKAMURA M.HASEGAWA S.KAWASAKI H.NAKASHIMA A.HIGASHIJIMA RIAM Kyushu University IGSES Kyushu University National Institute for Fusion Science Hiroshima University Kyoto University University of tsukuba

two-dimensional structure of density fluctuations is examined during the current jump phase, indicating a change from the open magnetic fields to the closed ones. During the smooth current ramp-up phase the two-dimensional contour of the LiI intensity shows vertically alignment, consistent with the magnetic surfaces. At the inflection point in Ip ramp-up the LiI intensity contour becomes flat in the observation regime and then suddenly a steep gradient and higher intensity regime are formed in the vertical direction. this higher intensity corresponds to a burst of LiI waveform. According to these changes in the contour, it is found that, within ~1 ms around the burst of LiI, a low frequency coherent wave with a long wavelength rapidly grows. the relations with other signals （magnetic flux and microwave stray power） are discussed with respect to the topological change in the magnetic configuration and mode conversion of the incident electromagnetic waves.

关键词： Li sheet beam density fluctuations current ramp-up spherical tokamak

Design Studies for Optimization of LHD-type Reactor FFHR

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Design Studies for Optimization of LHD-type Reactor FFHR

Comparison of luminescent properties of helicene-like bibenzothiophenes with o-carborane and 5,6-dicarba-nidodecaborane

Ninth China-Japan Symposium on Materials for Advanced Energy Systems and Fission & Fusion Engineering Jointed with CAS-JSPS Core-university Program Seminar on Fusion Materials, System and Design Integration

作者： Akio Sagara O.Mitarai S.Imagawa t.tanaka Y.Kozaki M.Kobayashi t.morisaki S.Masuzaki K.takahata H.tamura N.Yanagi K.Nishimura H.Chikaraishi S.Yamada S.Fukada A.Shishkin t.Watanabe Y.Igitkhanov t.Goto Y.Ogawa t.Muroga t.Mito O.Motojima FFHR design group National Institute for Fusion Science toki Gifu 509-5292 Japan Kyushyu tokai University 9-1-1 toroku Kumamoto 862-8652 Japan National Institute for Fusion Science toki Gifu 509-5292 Japan National Institute for Fusion Science toki Gifu 509-5292 Japan National Institute for Fusion Science toki Gifu 509-5292 Japan National Institute for Fusion Science toki Gifu 509-5292 Japan National Institute for Fusion Science toki Gifu 509-5292 Japan National Institute for Fusion Science toki Gifu 509-5292 Japan National Institute for Fusion Science toki Gifu 509-5292 Japan National Institute for Fusion Science toki Gifu 509-5292 Japan National Institute for Fusion Science toki Gifu 509-5292 Japan National Institute for Fusion Science toki Gifu 509-5292 Japan National Institute for Fusion Science toki Gifu 509-5292 Japan National Institute for Fusion Science toki Gifu 509-5292 Japan Kyushu University 6-10-1 Hakozaki.Fukuoka Fukuoka 812-8581 Japan Kharkov Institute of Physics and technology Kharkov-108 Ukraine National Institute for Fusion Science toki Gifu 509-5292 Japan Max-Planck-Institut für Plasmaphysik IPP-EURA tOM Ass. Greifswald Germany the University of tokyo 5-1-5 Kashiwa Chiba 277-8568 Japan the University of tokyo 5-1-5 Kashiwa Chiba 277-8568 Japan National Institute for Fusion Science toki Gifu 509-5292 Japan National Institute for Fusion Science toki Gifu 509-5292 Japan National Institute for Fusion Science toki Gifu 509-5292 Japan

An overview of recent activities on optimizing the base design of LHD-type helical power reactor FFHR is presented,including key design improvements on blanket and divertor configurations, neutronics performance,large... 详细信息

关键词： Design Studies for Optimization of LHD-type Reactor FFHR Reactor LHD

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Science China Chemistry 2018年第8期61卷 940-946页

作者： Kenta Nishino Kazushi Hashimoto Kazuo tanaka Yasuhiro morisaki Yoshiki Chujo Department of Polymer Chemistry Graduate School of Engineering Kyoto University Department of Applied Chemistry for Environment School of Science and Technology Kwansei Gakuin University

this article describes comparison of the anchoring effect on electronic properties of the helicene-like bibenzothiophene between o-carborane and 5,6-dicarba-nido-decaborane. the o-carborane and nido-decaborane-fused bibenzothiophenes were simultaneously obtained in the same reaction and successfully isolated. Initially, the X-ray single crystal analysis revealed that the helicene-like distorted structure was realized in the nido-decaborane-fused bibenzothiophene. From optical measurements in the solution state, distinct different characteristics depending on the type of anchors were observed. It was summarized that the absorption and luminescent properties originated from weak π-conjugation at the bibenzothiophene moiety in the o-carboranefused compound were obtained, whereas robust π-conjugation and significant emission from the intramolecular charge transfer state were detected from the nido-decaborane-fused compound. these data can be explained by the theoretical results that π-conjugation was restrictedly developed within the bibenzothiophene moiety in frontier orbitals of the o-carborane-fused compound. In contrast, π-conjugation can be constructed even through the distorted bibenzothiophene because of the nido-decaborane unit. Moreover, the intramolecular charge transfer state should be realized because of electronic interaction involving the nido-decaborane unit in the excited state. Furthermore, it was demonstrated that the nido-decaborane-fused compound possessed solid-state emission and mechanochromic luminescent properties. the π-conjugation on the distorted structure supported by the nido-decaborane anchor should play a significant role in suppressing aggregation-caused quenching followed by presenting solid-state emission with stimuli responsiveness.

关键词： carborane helicene mechanochromism aggregation-induced emission

Development of Polarized HD target for Future LEPS Experiments at SPring-8

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原子核物理评论 2009年第S1期26卷 79-82页

作者： H.Kohri M.Fujiwara K.Fukuda t.Kunimatsu C.morisaki t.Ohta K.S.Ueda M.Uraki M.Utsuro M.Yosoi Research Center for Nuclear Physics(RCNP) Osaka University College of Medical technology Kyoto University

We are carrying out hadron photoproduction experiments by using polarized photon beams at SPring-8 in Japan. In 2005,we started developing a polarized HD target for future experiments using both the polarized photon beams and the polarized target. the polarized HD target is an idealistic target for experiments observing reactions with small cross sections because the HD does not include heavy nuclei which produce many background events. the measurement of double polarization asymmetries is expected to give much important information to investigate the nucleon hidden structure,hadron photoproduction dynamics,and exotic hadron property. We report on the present status of the development of the polarized HD target at RCNP.

关键词： strangeness photon target

Formation of Edge transport Barriers by L-H transition and Large Reversed Plasma Current on LHD

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Plasma Science and technology 2006年第1期8卷 5-9页

作者： K. tOI S. OHDACHI F. WAtANABE K. NARIHARA t. morisaki 高翔 M. GOtO K. IDA S. MASUZAKI K. MIYAZAWA S. MOR.ItA S. SAKAKIBARA K. tANAKA t. tOKUZAWA K.W. WAtANABE 严龙文 M. YOSHINUMA National Institute for Fusion Science Toki Japan Department of Energy Science and Engineering Nagoya University Nagoya Japan Institute of Plasma Physics Chinese Academy of Science Hefei 230031 China Southwestern Institute of Physics Chengdu 610041 China

On the Large Helical Device （LHD） where nested magnetic surfaces are surrounded by the ergodic field layer, edge transport barrier （EtB） was produced in neutral-beam-injection （NBI） heated plasmas through transition and non-transition processes. the former case is the EtB formation by L-Htransition, where characteristics of L-H transition observed in a tokamak plasma are clearly recognized. the confinement improvement is the modest （- 10%）, compared with the ISS95 international stellarator scaling. the threshold power for the transition is comparable or slightly lower than the ItER scaling law established by tokamaks and compact tori. the EtB is formed inside the ergodic field layer of the vacuum field. the EtB formation destabilizes edge coherent modes such as m/n = 1/1, 2/3 and 1/2, of which rational surfaces are in the magnetic hill. the formed EtB is partially and transiently destroyed by these coherent edge MHD modes and edge localized modes （ELMs） typically observed in Ha signals. the latter EtB is observed in a plasma with large reversed NBI-driven current more than 100 kA at Bt = 1 t. In these plasmas, the edge magnetic shear is enhanced by the current and the rotational transform in the core region is expected to be appreciably reduced. thus reduced rotational transform in the plasma central region will enhance outward heat and particle fluxes toward ergodic edge layer. the EtB with steep electron temperature gradient up to - 5 keV/m is formed by blocking enhanced outward heat flux.

关键词： edge transport barrier ergodic field layer L-H transition ELMs edge MHD modes

Adminlstration of Hemoglobin Vesicle under Mechanical Ventilation Does Not Affect Lung Function

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Adminlstration of Hemoglobin Vesicle under Mechanical Ventil...

Review of Divertor Studies in LHD

第十一届国际人工血液大会

作者： Izumi Y Yamada t Ogawa EN morisaki H Sakai H Horinouchi H takeda J tsuchida E Kobayashi K Division of General thoracic Surgery Department of Anesthesia School of Medicine Keio UniversityTokyoJapan Advanced Research Institute for Sci and Eng Waseda UniversityTokyo Japan

＜正＞Hemoglobin Vesicle（HbV）contains concentrated hemoglobin solution within a phospholipid *** a resuscitative fluid,it will potentially be administered to patients receiving care in the intensive care unit,which includes mechanical *** did not affect lung function when administered under spontaneous breathing In this study,we administered HbV when the Iung was mechanically *** were mechanically

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Plasma Science and technology 2006年第1期8卷 14-18页

作者： t. morisaki S. MASUZAKI A. KOMORI N. OHYABU M. KOBAYASHI J. MIYAZAWA M. SHOJI 高翔 K. IDA K. IKEDA O. KANEKO K. KAWAHAtA S. KUBO S. MORItA K. NAGAOKA H. NAKANISHI K. NARIHARA Y. OKA M. OSAKABE B. J. PEtERSON S. SAKAKIBARA R. SAKAMOtO t. SHIMOZUMA Y. tAKEIRI K. tANAKA K. tOI, K. tSUMORI K. Y. WAtABABE t. WAtARI H. YAMADA I. YAMADA 严龙文杨青巍杨愚 Y.YOSHIMURA M. YOSHINUMA O. MOtOJIMA National Institute for Fusion Science Toki Gifu 509-5292 Japan Institute of Plasma Physics Chinese Academy of Sciences Hefei 230031 China Southwesteru Institute of Physics Chengdu 610041 China

In the Large Helical Device （LHD）, two different divertor configurations, i.e. helical divertor （HD） and local island divertor （LID）, are utilized to control the edge plasma. the HD with two X-points is an intrinsic divertor for heliotron devices, accompanied with a relatively thick ergodic layer outside the confinement region. Edge and divertor plasma behavior from low density to high density regimes is presented, referring to the divertor detachment. the effect of the ergodic layer on the edge transport is also discussed. On the other hand, the LID is an advanced divertor concept which realizes a high pumping efficiency by the combination of an externally induced magnetic island and a closed pumping system. Experimental results to confirm the fundamental divertor performance of the LID are presented.

关键词： LHD divertor ergodic layer magnetic island edge plasma

ICRF Heated Long-Pulse Plasma Discharges in LHD

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Plasma Science and technology 2006年第1期8卷 28-32页

作者： R. KUMAZAWA t. SEKI t. MUtOH K. SAItO t. WAtARI Y. NAKAMURA M. SAKAMOtO t. WAtANABE S. KUBO t. SHIMOZUMA Y. YOSHIMURA H. IGAMI Y. tAKEIRI Y. OKA K. tSUMORI M. OSAKABE K. IKEDA K. NAGAOKA O. KANEKO J. MIYAZAWA S. MORItA K. NARIHARA M. SHOJI S. MASUZAKI M. GOtO t. morisaki B. J. PEtERSON K. SAtO t. tOKUZAWA N. ASHIKAWA K. NISHIMURA H. FUNABA H. CHIKARAISHI t. NOtAKE Y. tORII H. OKADA M. ICHIMURA H. HIGAKI Y. tAKASE H. KASAHARA F. SHIMPO G.NOMURA C.tAKAHASHI M.YOKOtA A. KAtO 赵燕平 J. S. YOON J. G. KWAK H. YAMADA K. KAWAHAtA N. OHYABU K. IDA Y. NAGAYAMA N. NODA A. KOMORI S. SUDO O. MOtOJIMA National Institute for Fusion Science Toki Japan Kyusyu University Kasuga Japan Nagoya University Faculty of Engineering Nagoya Japan Kyoto University Institute of Advanced Energy Uji Japan tsukuba University Plasma Research Center Tsukuba Japan tokyo University Graduate School of Frontier Sciences Tokyo Japan Institute of Plasma Physics Chinese Academy of Sciences Hefei 230031 China KAERI 150 Deogjin-dong Yuseong-gu Daejeon Korea Rep.

A long-pulse plasma discharge for more than 30 min. was achieved on the Large Helical Device （LHD）. A plasma of ne = 0.8 × 10^19 m^-3 and t10 = 2.0 keV was sustained with PICH = 0.52 MW, PECH = 0.1 MW and averaged PNBI = 0.067 MW. total injected heating energy was 1.3 G J, which was a quarter of the prepared RF heating energy. One of the keys to the success of the experiment was a dispersion of the local plasma heat load to divertors, accomplished by shifting the magnetic axis inward and outward.

关键词： helical/stellarator configuration ICRF heating steady state operation