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plasma Science and Technology 2005年第5期7卷 3057-3061页

作者：宋云涛 S.Nishio Institute of plasma Physics Chinese Academy of Sciences department of fusion plasma research of japan atomic energy research institutenaka-machi Naka-gun Ibaraki-ken 311-0193 Japan

High-pressure gas injection has proved to be an effective disruption mitigation tech- nique in DIII-D tokamak experiments. If the method can be applied in future tokamak reactors not only for disruption mitigation but also for plasma termination and fueling, it will have an attractive advantage over the pellet and liquid injection from the viewpoint of economy and engineering design. In order to investigate the feasibility of this option, a study has been carried out with relevant parameters for conveying tubes of different geometrical sizes and for different gases. These parameters include pressure drop, lagger time after the valve＇s opening, gas diffusion in an ultra-high vacuum condition, and particle number contour.

关键词： tokamak reactor disruption mitigation fueling gas injection

Buckling Analysis of TF Coil Inner Leg for Central Solenoidless Tokamak

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plasma Science and Technology 2006年第4期8卷 468-472页

作者：宋云涛杨庆喜 Satoshi NISHIO Institute of plasma Physics Chinese Academy of SciencesHefei 230031China department of fusion plasma research Japan Atomic Energy Research InstituteNaka-machiNaka-gunIbaraki-ken 311-0193Japan

The central post is one of the critical components for the low aspect ratio tokamak, which endures not only a tremendous ohmic heating because it carries a rather high current, but also a large neutron heating and irradiation owing to the plasma operation. The DS copper alloy Glidcop AL-25[8] was chosen as the conductor material for its adequate mechanical properties and physics properties. The central post has a cylindrical structure with lots of cooling channels. The length of the central post for the next generation of nuclear fusion spherical tokamaks will be more than 10 m or 20 m. The structural stability is very crucial. When the applied load is larger than the structure critical buckling load, the device will lose its stability and collapse. In order to calculate the critical buckling load, a 1/6-segment finite element model was used and the force acting on the central post was simulated. The results showed that the vertical compressive stresses mainly affect the stability of the central post. The linear buckling analysis results with finite element method based on small deformation theory were given in this paper. The relation curves and functions for buckling factor, depending on the different lengths and the radius of the central post, the diameter of cooling channel and the maximum allowable current density, were also shown.

关键词： low aspect ratio tokamak toroidal field coil central post buckling analysis

A Consideration on Increasing Current Density in Normal Conducting Toroidal Field Coil for Spherical Tokamak Power Plant

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plasma Science and Technology 2005年第2期7卷 2731-2733页

作者：宋云涛西尾敏 Institute of plasma Physics Chinese Academy of Sciences Hefei 230031China department of fusion plasma research of japan atomic energy research Institute Naka-machi Naka-gunIbaraki-ken 311-0193Japan

The center post is the most critical component as an inboard part of the toroidal field coil for the low aspect ratio tokamak. During the discharge it endures not only a tremendous ohmic heating owing to its carrying a rather high current but also a large nuclear heating and irradiation owing to the plasma operation. All the severe operating conditions, including the structure stress intensity and the stability of the structure, largely limit the maximum allowable current density. But in order to contain a very high dense plasma, it is hoped that the fusion power plant system can operate with a much high maximum magnetic field BT ≥12 T-15 T in the center post. A new method is presented in this paper to improve the maximum magnetic field up to 17 T and to investigate the possibility of the normal conducting center post to be used in the future fusion tokamak power plant.

关键词： low aspect ratio tokamak power plant toroidal field coil center post high magnetic field

Deuterium Retention and Physical Sputtering of Low Activation Ferritic Steel

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plasma Science and Technology 2005年第2期7卷 2737-2740页

作者： T.Hino K.Yamaguchi Y.Yamauchi Y.Hirohata K.Tsuzuki Y.Kusama department of Nuclear Engineering Hokkaido University Sapporo060-8628 JapanDepartment of Nuclear Engineering Hokkaido UniversitySapporo060-8628 JapanDepartment of Nuclear Engineering Hokkaido UniversitySapporo060-8628 JapanDepartment of Nuclear Engineering Hokkaido UniversitySapporo060-8628 JapanJapan Atomic Energy Research Institute NakaIbaraki-ken311-0193 JapanJapan Atomic Energy Research Institute NakaIbaraki-ken311-0193 Japan

Low activation materials have to be developed toward fusion demonstrationreactors. Ferritic steel, vanadium alloy and SiC/SiC composite are candidate materials of the firstwall, vacuum vessel and blanket components, respectively. Although changes of mechanical-thermalproperties owing to neutron irradiation have been investigated so far, there is little data for theplasma material interactions, such as fuel hydrogen retention and erosion. In the present study,deuterium retention and physical sputtering of low activation ferritic steel, F82H, wereinvestigated by using deuterium ion irradiation apparatus. After a ferritic steel sample wasirradiated by 1.7 keV D^+ ions, the weight loss was measured to obtain the physical sputteringyield. The sputtering yield was 0.04, comparable to that of stainless steel. In order to obtain theretained amount of deuterium, technique of thermal desorption spectroscopy (TDS) was employed to theirradiated sample. The retained deuterium desorbed at temperature ranging from 450 K to 700 K, inthe forms of DHO, D_2, D_2O and hydrocarbons. Hence, the deuterium retained can be reduced by bakingwith a relatively low temperature. The fluence dependence of retained amount of deuterium wasmeasured by changing the ion fluence. In the ferritic steel without mechanical polish, the retainedamount was large even when the fluence was low. In such a case, a large amount of deuterium wastrapped in the surface oxide layer containing O and C. When the fluence was large, the thickness ofsurface oxide layer was reduced by the ion sputtering, and then the retained amount in the oxidelayer decreased. In the case of a high fluence, the retained amount of deuterium became comparableto that of ferritic steel with mechanical polish or SS 316 L, and one order of magnitude smallerthan that of graphite. When the ferritic steel is used, it is required to remove the surface oxidelayer for reduction of fuel hydrogen retention. Ferritic steel sample was exposed to the envi

关键词： ferritic steel fuel hydrogen retention sputtering yield first wall fusionreactor

Self-Injection and Acceleration of Monoenergetic Electron Beams from Laser Wakefield Accelerators in a Highly Relativistic Regime

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Chinese Physics Letters 2008年第8期25卷 2938-2941页

作者： H.Yoshitama T.Kameshima 3谷渝秋郭仪焦春晔刘红杰彭翰生唐传铭王小东温贤伦温天舒吴玉迟张保汉朱启华黄晓军安维民黄文会唐传祥林郁正王小东陈黎明 H.Kotaki M.Kando K.Nakajima department of Accelerator Science The Graduate University for Advanced Studies 1-10ho Tsukuba Ibaraki 305-0801 Japan High energy Accelerator research Organization 1-10ho Tsukuba Ibaraki 305-0801 Japan Laser fusion research Center China Academy of Engineering Physics Sichuan 621900 department of Engineering Physics Tsinghua University Beijing 100084 University of Southern California Los Angels CA90089-0484 USA Kansai Photon Science Institute Japan Atomic Energy Agency Kyoto 619-0215 Japan

Self-injection and acceleration of monoenergetic electron beams from laser wakefield accelerators are first investigated in the highly relativistic regime, using 100 TW class, 27 fs laser pulses. Quasi-monoenergetic multi- bunched beams with energies as high as multi-hundredMeV are observed with simultaneous measurements of side-scattering emissions that indicate the formation of self-channelfing and self-injection of electrons into a plasma wake, referred to as a ＇bubble＇. The three-dimensional particle-in-cell simulations confirmed multiple self-injection of electron bunches into the bubble and their beam acceleration with gradient of 1.5 GeV/cm.

关键词： PULSE INTERACTION plasmaS

Application of Kelvin Probe to Studies of fusion Reactor Materials under Irradiation

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plasma Science and Technology 2005年第4期7卷 2982-2984页

作者：罗广南 K.Yamaguchi T.Terai M.Yamawaki department of Quantum Engineering and Systems Science Graduate School of Engineering The University of Tokyo7-3-1 KongoBunkyo-kuTokyo 113-8656Japan Neutron Science Rearch Center japan atomic energy research Institute 2-4 ShirakataTokai-muraIbaraki319-1195Japan

Recently, the work function （WF） changes in metallic and ceramic materials to be potentially used in future fusion reactors have been examined by means of Kelvin probe （KP）, under He ion irradiation in high energy （MeV） and / or low energy （500 eV） ranges. The results of polycrystalline Ni samples indicate that the 1 MeV beam only induces decrease in the WF within the experimental fluence range; whereas the irradiation of 500 eV beam results in decrease in the WF firstly, then increase till saturation. A dual layer surface model is employed to explain the observed phenomena, together with computer simulation results by SRIM code. Charges buildup on the surface of lithium ceramics has been found to greatly influence the probe output, which can be explained qualitatively using a model concerning an induction electric field due to external field and free charges on the ceramic surface.

关键词： fusion reactor materials work function irradiation

Simulation of fusion plasmas:Current Status and Future Direction

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plasma Science and Technology 2007年第3期9卷 312-387页

作者： D.A.Batchelor M.Beck A.Becoulet R.V.Budny C.S.Chang P.H.Diamond J.Q.Dong G.Y.FU A.Fukuyama T.S.Hahm D.E.Keyes Y.Kishimoto S.Klasky L.L.Lao K.Li Z.Lin B.Ludaescher J.Manickam N.Nakajima T.Ozeki N.Podhorszki W.M.Tang M.A.Vouk R.E.Waltz S.J.Wang H.R.Wilson X.Q.Xu M.Yagi F.Zonca Oak Ridge National Laboratory Oak RidgeTN 37831USA 1122 Volunteer Blvd Suite 203KnoxvilleTN 37996-3450USA AssociationEURATOM-CEA sur la Fusio n Contr■lée CEA Cadarache13108 Saint Paul lez Durance CedexFrance Princeton plasma Physics Laboratory Princeton UniversityPrincetonNJ 08543USA Courant Institute of Mathematical Sciences New York University251 Mercer StreetNew YorkNY 10012USA University of California at San Diego Dept.of Physics and Center for Astrophysics and Space SciencesLa JollaCA 92093USA Southwestern Institute of Physics Chengdu 610041China department of Nuclear Engineering Kyoto UniversityKyoto 606-8501Japan Columbia University Department of Applied Physics and Applied MathematicsMC 4701New YorkNY 10027USA department of Fundamental energy Science Graduate School of Energy ScienceKyoto UniversityGokashoUjiKyoto 611-0011Japan General atomics P.O.Box 85608San DiegoCA 92186USA department of Computer Science Princeton University PrincetonNJ 08544USA department of Physics and Astronomy University of CaliforniaIrvineCA 92697USA department of Computer Science University of California DavisCA95616USA National Institute for fusion Science TokiGifu 509-5292Japan japan atomic energy Agency Naka Fusion Research EstablishmentNaka-machiIbaraki-kenJapan department of Computer Science North Carolina State UniversityRaleighNC 27695USA department of Physics Fudan University200433 ShanghaiChina department of Physics University of YorkHeslingtonYork YO10 5DD UK Lawrence Livermore National Laboratory LivermoreCA 94550USA research Institute for Applied Mechanics Kyushu UniversityKasuga 816-8580Japan Associazione Euratom-ENEA sulla fusione CR FrascatiCasella Postale 65-00044FrascatiItaly

I. Introduction (Z. Lin, G. Y. Fu, J. Q. Dong) II. Role of theory and simulation in fusion sciences 1. The Impact of theory and simulation on tokomak experiments (H. R. Wilson, T.S. Hahm and F. Zonca) 2. Tokomak Transport Physics for the Era of ITER: Issues for Simulations (P.H. Diamond and T.S. Hahm) III. Status of fusion simulation and modeling 1. Nonlinear Governing Equations for plasma Simulations (T. S. Hahm) 2. Equilibrium and stability (L.L. Lao, J. Manickam) 3. Transport modeling (R.E. Waltz) 4. Nonlinear MHD (G.Y. Fu) 5. Turbulence (Z. Lin and R.E. Waltz) 6. RF heating and current drive (D.A. Batchelor) 7. Edge physics Simulations (X.Q. Xu and C.S. Chang) 8. Energetic particle physics (F. Zonca, G.Y. Fu and S.J. Wang) 9. Time-dependent Integrated Modeling (R.V. Budny) 10. Validation and verification (J. Manickam) IV. Major initiatives on fusion simulation 1. US Scientific Discovery through Advanced Computing (SciDAC) Program & fusion energy Science (W. Tang) 2. EU Integrated Tokamak Modelling (ITM) Task Force (A. Becoulet) 3. fusion Simulations Activities in japan (A. Fukuyama, N. Nakajima, Y. Kishimoto, T. Ozeki, and M. Yagi) V. Cross-disciplinary research in fusion simulation 1. Applied mathematics: Models, Discretizations, and Solvers (D.E. Keyes) 2. Computational Science (K. Li) 3. Scientific Data and Workflow Management (S. Klasky, M. Beck, B. Ludaescher, N. Podhorszki, M.A. Vouk) 4. Collaborative tools (J. Manickam)

关键词： mode ITER

3 - 28 Recent Progress of Study on Radiation Damage in fusion Reactor Materials by Utilizing Ion Accelerators

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IMP & HIRFL Annual Report 2013年第1期 95-97页

作者： Zhang Chonghong Yang Yitao Song Yin Zhang Liqing Chen Jiachao J. Jang A. Kimura Ma Hongji Paul Scherrer Institut Villigen PSI Switzerland. Korea atomic energy research Institute Daejeon South Korea. Institute of Advanced energy Kyoto University Kyoto Japan. department of Technical Physics Peking University Beijing China.

Experiments on synthesis of the heaviest elements at RIKEN

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Experiments on synthesis of the heaviest elements at RIKEN

Properties of vapor-deposited and solution-processed targets for laser-driven inertial confinement fusion experiments

6th China-japan Joint Nuclear Physics Symposium

作者： K.Morimoto K.Morita D.Kaji A.Yoneda H.Haba T.Akiyama N.Sato S.Goto E.Ideguchi K.Katori H.Kikunaga H.Koura H.Kudo T.Ohnishi A.Ozawa T.Suda K.Sueki F.Tokanai T.Yamaguchi A.Yoshida RIKEN (The Institute of Physical and Chemical research) Wako Saitama 351-0198Japan RIKEN (The Institute of Physical and Chemical research) Wako Saitama 351-0198Japan Department of PhysicsSaitama UniversitySakuraSaitama 338-8570Japan RIKEN (The Institute of Physical and Chemical research) Wako Saitama 351-0198Japan Departent of PhysicsTohoku UniversitySendalMiyagi 980-8578Japan department of Chemistry Niigata University IkarashiNiigata 950-2181Japan Center for Nuclear Science University of Tokyo Wako-shiSaitama 351-0198Japan RIKEN (The lnstitute of Physical and Chemical research) Wako Saitama 351-0198Japan japan atomic energy Agency (JAEA) Naka-gun Ibaraki 319-1184Japan department ofChemistry Niigata University IkarashiNiigata 950-2181Japan University of Tsukuba Tsukuba lbaraki 305-8577Japan department of Physics Yamagata University ShirakawaYamagata 990-8560Japan department of Physics Saitama University SakuraSaitama 338-8570Japan

In the Institute of Physical and Chemical research(RIKEN),using high intensity heavy ion beams from the R/KEN Linear Accelerator,productions and decays of isotopes of the heaviest elements have been investigated by using the gas-filled recoil separator,*** isotopes studied were Hs,Ds,Rg,112,and 113,*** on the observed decay chains consisting of consecutive alpha decays connected to the previously known alpha decays or spontaneous fissions,assignments of the initially produced isotopes were *** data with the atomic number from 108 to 112,agree well with the data previously *** production cross section of the isotope 113 of the 113th element have reached around 32 tl0 which shows the simple decrease of the cross section with the increase of the atomic number. The isotopes were produced,for the first time in the In evaporation channel from heavy-ion induced fusion reaction.

关键词： 277112 278113 production and decay gas-filled recoil separator

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Matter and Radiation at Extremes 2018年第6期3卷 312-321页

作者： D.R.Harding M.J.Bonino W.Sweet M.Schoff A.Greenwood N.Satoh M.Takagi A.Nikroo Laboratory for Laser Energetics University of Rochester250 East River RoadRochesterNY 14623-1299USA department of Chemical Engineering University of RochesterRochesterNY 14623-1299USA General atomics 3550 General Atomics CourtSan DiegoCA 92121-1122USA Industrial Development Center Central Research LaboratoryHamamatsu Photonics K.K.Hamamatsu CityShizuoka Pref.431-1202Japan Institute of Laser Engineering Osaka University2e6 YamadaokaSuitaOsaka 565-0871Japan Lawrence Livermore National Laboratory P.O.Box 808LivermoreCA94550USA

Targets for low-adiabat direct-drive-implosion experiments on OMEGA must meet rigorous specifications and tight tolerances on the diameter,wall thickness,wall-thickness uniformity,and presence of surface *** these,restrictions on the size and number of defects(bumps and depressions)on the surface are the most *** properties of targets that are made using vapor-deposition and solution-based microencapsulation techniques are *** were characterized using confocal microscopy,bright-and dark-field microscopy,atomic force microscopy,electron microscopy,and *** technique has merits and limitations,and a combination of these techniques is necessary to adequately characterize a *** main limitation with the glow-discharge polymerization(GDP)method for making targets is that it produces hundreds of domes with a lateral dimension of 0.7-2 μ*** these targets reduces the size of some but not all domes,but it adds scratches and grooves to the ***-made polystyrene shells lack the dome features of GDP targets but have hundreds of submicrometer-size voids throughout the wall of the target;a few of these voids can be as large as~12 μm at the surface.

关键词： Vapor-deposition Direct-drive target OMEGA Target characterization Solution-based microencapsulation