T. Nagashima

ORCID: 0000-0001-9125-8469
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About
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Research Areas
  • Magnetic confinement fusion research
  • Particle accelerators and beam dynamics
  • Superconducting Materials and Applications
  • Ionosphere and magnetosphere dynamics
  • Gyrotron and Vacuum Electronics Research
  • Fusion materials and technologies
  • Logic, Reasoning, and Knowledge
  • Plasma Diagnostics and Applications
  • Particle Accelerators and Free-Electron Lasers
  • Laser-Plasma Interactions and Diagnostics
  • Logic, programming, and type systems
  • Advanced Algebra and Logic
  • Nuclear reactor physics and engineering
  • Game Theory and Applications
  • Mathematics and Applications
  • Dust and Plasma Wave Phenomena
  • Nuclear Materials and Properties
  • Lubricants and Their Additives
  • Metal and Thin Film Mechanics
  • Tribology and Lubrication Engineering
  • Power System Optimization and Stability
  • Diamond and Carbon-based Materials Research
  • Nuclear Physics and Applications
  • Pulsed Power Technology Applications
  • Congenital Diaphragmatic Hernia Studies

Shibaura Institute of Technology
2003-2025

Kurashiki Central Hospital
2022

National Institute for Materials Science
1986-2011

Panasonic (Japan)
1976-2007

Toyo University
2004

Research Institute of Ceramics
2003

Honda (Japan)
2003

St. Marianna University School of Medicine
1993-2001

Japan Atomic Energy Agency
1978-2000

Honda (United States)
1992-1999

It is observed that the waves launched from a phased array antenna of four waveguides couple effectively with electrons under condition $\frac{{\ensuremath{\omega}}_{0}}{{\ensuremath{\omega}}_{1h}(0)}\ensuremath{\gtrsim}2.0$. This coupling generates rf-driven current, rather than heating bulk electrons, and current/rf-power ratio 110 A/kW was obtained rf power 125 kW radiated into plasma which included appreciable suprathermal electrons.

10.1103/physrevlett.45.716 article EN Physical Review Letters 1980-09-01

Experimental data are presented which show that during lower-hybrid, radio-frequency heating of the Princeton University adiabatic toroidal compressor tokamak, parametric instabilities excited, and ion correlates with presence spectra. A theoretical interpretation is presented.

10.1103/physrevlett.38.230 article EN Physical Review Letters 1977-01-31

Optical correlation-domain reflectometry (OCDR), widely recognized for its ability to pinpoint the locations and reflectivities of faulty connections other reflective points along optical fibers, offers advantages random accessibility, real-time operation, cost-effectiveness. In Brillouin OCDR, commonly employed distributed strain temperature sensing, a well-known challenge is trade-off between spatial resolution measurement range. To overcome this limitation, double-modulation scheme has...

10.1587/transele.2024ecs6013 article EN IEICE Transactions on Electronics 2025-01-01

Ion heating by irradiation of rf fields in the ion-cyclotron range frequencies is investigated using several diagnostic techniques. It shown that substantial bulk ions can be achieved this method.

10.1103/physrevlett.39.31 article EN Physical Review Letters 1977-07-04

Decay spectra during the rf heating were identified as parametric decay into cold lower-hybrid waves and ion-cyclotron at plasma surface. The instabilities absorbed some fraction of power, hence they affected heating. However, did not prevent penetration lower hybrid wave to center. Drastic reduction was obtained when resonant condition destroyed.

10.1103/physrevlett.43.586 article EN Physical Review Letters 1979-08-20

10.4271/1999-01-3468 article EN SAE technical papers on CD-ROM/SAE technical paper series 1999-10-25

10.1007/bf00370838 article EN Studia Logica 1996-10-01

Results from the JFT−2a (DIVA) experiments made with a separatrix magnetic surface are described. The main conclusions are: (1) A is stably located inside material surface. (2) plasma enclosed in similar to that of conventional tokamak as far magnetohydrodynamic properties concerned. (3) Measured parameters column consistent those expected tokamak. (4) electron density and temperature scrape-off layer about ten times less than values at center column. (5) Heat particle fluxes divertor region...

10.1063/1.861335 article EN The Physics of Fluids 1976-10-01

In order to improve the safe handling and control of tritium for ITER fuel cycle, effective in situ accounting methods have been developed at Tritium Process Laboratory Japan Atomic Energy Research Institute under one ITER-EDA R&D tasks. The remote multilocation analysis process gases by an application laser Raman spectroscopy tested could provide a measurement hydrogen isotope with detection limit 0.3 kPa analytical periods 120 s. An inventory `self-assaying' storage bed 25 g capacity...

10.1088/0029-5515/40/3y/312 article EN Nuclear Fusion 2000-03-01

Results are presented of the first Lower Hybrid Current Drive (LHCD) experiments in JT-60. 2 MA RF driven current is successfully produced for time a reactor grade tokamak. The magnetic divertor works quite well eliminating impurities released by carrying fast electrons which have allowed generation relevant very low density plasma. efficiency defined as ηCD = eRIRF/PLH(1019 m−3 A·W−1), reaches values 0.8 to 1.7. NBI heating enhances drive factor 1.5, and LHCD improves confinement high power...

10.1088/0029-5515/28/8/003 article EN Nuclear Fusion 1988-08-01

A multijunction launcher was designed and constructed to improve the directivity of launched waves with a narrow wave number spectrum by dividing each main waveguide into three secondary waveguides. The coupling characteristics agree fairly well theory, power up 2 MW obtained after few days conditioning. dependence current drive efficiency ηCD (= neIRFR/PLH) on studied changing phase difference between adjacent It found that high is interacting fast electrons as far plasma travel. maximum...

10.1088/0029-5515/29/10/016 article EN Nuclear Fusion 1989-10-01

A Langmuir probe is used to study the plasma behaviour in scrape-off layer of JFT-2a, (a Tokamak with an axisymmetric divertor). The measurements reveal particle fluxes divertor and wall as well cross-field profiles density potential layer. On basis these measurements, diffusion coefficient efficiency are estimated. existence magnetic limiter also verified by method.

10.1088/0032-1028/20/8/003 article EN Plasma Physics 1978-08-01

Neutral-beam injection experiments on ATC have resulted in net power deposited the plasma of up to 230 kW. The ions is large compared that from ohmic heating. For a variety beam and ion species, increase temperature proportional power.

10.1088/0029-5515/16/3/018 article EN Nuclear Fusion 1976-07-01

Recent lower hybrid current drive (LHCD), and heating (LHH) experiments on JT-60 are reported. The product of neRpIRF approximately 12.5*1019 m-2 MA was achieved at the LH power 4.5 MW, CD efficiency, energy confinement, global balance heat load divertor plates were investigated in high LHCD plasmas. Nearly steady state H-mode discharges found during with two different frequency injections. Sawtooth suppression NB heated plasmas by have shown an improvement confinement near plasma center....

10.1088/0741-3335/32/11/003 article EN Plasma Physics and Controlled Fusion 1990-11-01

10.1023/a:1004975724824 article EN Studia Logica 1997-01-01

ICRF heating of impurity-free tokamak plasmas is studied in DIVA. The frequency fixed at 25 MHz, which a second-harmonic cyclotron deuteron with toroidal magnetic field 16.4 kG. BT and the ratio proton-to-deuteron density p are varied over ranges 12 ⩽ 19 kG 2 ⪅ 40%, respectively. most favourable ion obtained = 18 5 ∼ 10%. Ion temperature increases from 200 to 300 eV were measured by charge-exchange neutral analysis also spectroscopy, where 100 kW RF net power applied. results consistent...

10.1088/0029-5515/19/11/009 article EN Nuclear Fusion 1979-11-01

Some experimental informations have been obtained concerning the particle and heat transport during lower hybrid heating in JFT-2 tokamak. The cross field coefficients are determined from plasma parameters a scrape-off layer, add losses to limiter wall also estimated experimentally. It is shown that heatting does not give serious effects on confinement, if effective ion performed successfully main plasma.

10.1143/jpsj.48.1333 article EN Journal of the Physical Society of Japan 1980-04-01

Beam acceleration by heating in the second-harmonic ion cyclotron range of frequency (ICRF) combination with hydrogen neutral beam injection (NBI) was investigated JT-60 tokamak. The energy spectra accelerated fast ions were measured a charge exchange analyser whose line sight intersected specific lines plasma core order to obtain required information. dependences tail temperature on various parameters (electron density, NBI power and toroidal phasing antenna) examined. Optimized conditions...

10.1088/0029-5515/31/1/008 article EN Nuclear Fusion 1991-01-01
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