A5035488630- Magnetic confinement fusion research
- Superconducting Materials and Applications
- Fusion materials and technologies
- Crystallization and Solubility Studies
- X-ray Diffraction in Crystallography
- Ionosphere and magnetosphere dynamics
- ATP Synthase and ATPases Research
- Particle accelerators and beam dynamics
- Laser-Plasma Interactions and Diagnostics
- Plasma Diagnostics and Applications
- Mitochondrial Function and Pathology
- Crystallography and molecular interactions
- Nuclear reactor physics and engineering
- Metabolism and Genetic Disorders
- Monoclonal and Polyclonal Antibodies Research
- Enzyme Structure and Function
- Protein Structure and Dynamics
- Heat shock proteins research
- Glycosylation and Glycoproteins Research
- Biochemical and Molecular Research
- Laser-induced spectroscopy and plasma
- Solar and Space Plasma Dynamics
- Head and Neck Cancer Studies
- Autopsy Techniques and Outcomes
- Particle Detector Development and Performance
National Institutes for Quantum Science and Technology
2016-2025
Chiba University
2021-2024
National Institute for Fusion Science
2021-2024
Juntendo University Urayasu Hospital
2022-2023
Fusion Academy
2019-2023
Fusion (United States)
2019-2023
Ohtsuka Eye Hospital
2023
Kyushu University
2009-2022
Juntendo University
2022
National Centre for Nuclear Research
2021
Abstract Progress in physics understanding and theoretical model development of plasma transport confinement (TC) the ITPA TC Topical Group since publication ITER Physics Basis (IPB) document (Doyle et al 2007 Nucl. Fusion 47 S18) was summarized focusing on contributions to burning prediction control. This paper provides a general streamlined overview advances that were mainly led by joint experiments activities for last 15 years (see JEX/JA table appendix). starts with scientific strategy...
With WEST (Tungsten Environment in Steady State Tokamak) (Bucalossi et al 2014 Fusion Eng. Des. 89 907–12), the Tore Supra facility and team expertise (Dumont Plasma Phys. Control. 56 075020) is used to pave way towards ITER divertor procurement operation. It consists implementing a configuration installing ITER-like actively cooled tungsten monoblocks tokamak, taking full benefit of its unique long-pulse capability. user platform, open all partners. This paper describes physics basis WEST:...
The JT-60SA device has been designed as a highly shaped large superconducting tokamak with variety of plasma actuators (heating, current drive, momentum input, stability control coils, resonant magnetic perturbation W-shaped divertor, fuelling, pumping, etc) in order to satisfy the central research needs for ITER and DEMO. In ITER- DEMO-relevant parameter regimes DEMO-equivalent shapes, quantifies operation limits, responses operational margins terms MHD stability, transport confinement,...
Abstract Construction of the JT-60SA tokamak was completed on schedule in March 2020. Manufacture and assembly all main components satisfied technical requirements, including dimensional accuracy functional performances. Development plasma heating systems diagnostics have also progressed, demonstration favourable electron cyclotron range frequency (ECRF) transmission at multiple frequencies achievement long sustainment a high-energy intense negative ion beam. operation control has been...
<b><i>Purpose:</i></b> To compare aqueous humor levels of various cytokines between patients with age-related macular degeneration (AMD) and cataract patients. <b><i>Methods:</i></b> Thirteen eyes wet-type AMD (AMD group) 14 (cataract were studied. Aqueous 11 factors (vascular endothelial growth factor receptors, factors, inflammatory factors) measured by the suspension array method. <b><i>Results:</i></b> vascular...
The characteristics of momentum transport and plasma rotation in the toroidal direction are studied, using near-perpendicular neutral beam injection (PERP-NBI), co tangential counter (CTR) NBI JT-60U. Diffusive non-diffusive terms evaluated from transient analysis by source modulation. Fast ion losses due to field ripple, which locally induces edge CTR rotation, used as a novel source. Parameter dependence these coefficients i.e. diffusivity (χϕ) convection velocity (Vconv), relation between...
The toroidal plasma rotation generated by the external momentum input and itself (intrinsic rotation) has been separated through a novel transport analysis in JT-60U tokamak device. rotation, which is not determined coefficients input, observed. It found that this intrinsic locally local pressure gradient increases with increasing gradient. This trend almost same for various plasmas: low high confinement mode, co counterrotating plasmas.
Significant progress in the extension of pulse durations powerful negative ion beams has been made to realize neutral beam injectors for JT-60SA and ITER. In order overcome common issues long-pulse production/acceleration ITER, new technologies have developed source MeV accelerator Japan Atomic Energy Agency.
The mechanism of improving energy confinement with argon seeding at high density has been investigated in JT-60U. Better is sustained by accompanied higher core and pedestal temperatures. electron profiles become flatter increasing conventional H-mode plasmas, whereas peaked are maintained seeding. Density peaking dilution effects lower the a given averaged density. seeded which than that plasmas deuterium puff, enables temperature to be higher, increase pressure small. High boundary...
A 28-year-old woman experienced gross hematuria after the administration of second dose an messenger ribonucleic acid (mRNA) vaccine (BNT162b2). She was diagnosed with Immunogloblin nephropathy (IgAN) by a renal biopsy two weeks vaccination, which revealed mild increase in mesangial cells and matrix co-depositions galactose-deficient IgA1 C3 region. The proteinuria gradually improved without any medication, suggesting that immune activation mRNA may not elicit continuous disease progression...
The driving mechanism of toroidal rotation and the momentum transport are studied on JT-60U in relation to direction antiparallel plasma current, i.e. counter (CTR) direction, with near-perpendicular neutral beam (PERP-NB) injection. Fast ion losses due field ripple induce CTR peripheral region, magnitude PERP-NBs reduces by installing ferritic steel tiles as a consequence reduction losses. It is also found that velocity profiles core region can be explained considering diffusivity...
Abstract Plasma with an internal transport barrier (ITB) will be developed in JT-60SA as attractive operation appropriate for a steady-state fusion reactor. To achieve the ITB plasma while avoiding magnetohydrodynamic instabilities, it is advantageous to simultaneously control safety factor ( q ) profile and normalized beta <?CDATA $\beta_\mathrm{N}$?> <mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML" overflow="scroll"> <mml:msub> <mml:mi>β</mml:mi> <mml:mrow> <mml:mi...
Abstract This paper reports on the evaluation of diamagnetic energy using loops in JT-60SA, largest operating tokamak world, and revisits physics behind poloidal beta (βp) internal inductance (li). During first operation phase measurements were utilized assessing parameters related to plasma equilibrium, such as stored energy, βp li. The evaluated is above 200 kJ with 1 MJ electron cyclotron heating, we observed li rise from around unity 2 during current ramp- down phase. successfully...
Abstract In the control of large superconducting tokamaks, particularly for devices like DEMO reactors, where no stabilizing plates or in-vessel coils due to existence tritium blankets, position, shape, and current plasmas must be controlled solely with coils, which we developed novel schemes [S. Inoue et al., Nuclear Fusion 61, 096009 (2021)]; an adaptive voltage allocation (AVA) scheme automatically allocates power supply voltages plasma position/shape control, a robust last closed flux...
We have developed a two-color CO2 laser interferometer in JT-60SA, which features long transmission line and long-time stabilization system. inject two beams with an optimized beam size into the plasma of JT-60SA. A newly axis stabilizing system stabilizes to plasma, constitutes one fourth total length 214 m, for more than 11 hours, ensuring no loss during integrated commissioning phase It is possible measure line-integrated electron densities JT-60SA plasmas resolution 2 × 1019 m−2. The...
Abstract Characteristics and operational regimes of electron density, temperature, energy confinement have been investigated in the JT-60SA first plasma operation phase. Working gases for these discharges are hydrogen (H 2 ) helium (He). A current I p 1.2 MA has achieved at a toroidal magnetic field B T T. In = 1 MA, line-averaged density ¯n e 2.7 × 10 18 – 5.2 m −3 He-gas injected 2.5 6.5 H -gas plasma. maximum temperature this phase is 2.0 keV core region case He-gas-injection 1.13-MW...
Abstract Stable MA-class divertor plasmas have been achieved in the JT-60SA first plasma campaign based on developed control schemes and careful assessment before operation. Fundamental characteristics parameter regimes examined. The breakdown was obtained at low toroidal electric field of 0.12-0.15 V/m with a trapped particle configuration an Electron Cyclotron Heating (ECH) assist. EC assisted E|| also null by reducing residual poloidal magnetic (∼1 mT) optimizing initial coil voltage...
The effects of toroidal rotation and field (TF) ripple on the edge pedestal structure edge-localized-modes (ELMs) were examined in JT-60U. amplitude TF was changed by installation ferritic steel tiles (FSTs). profile VT became less counter with FSTs, particularly case where co-NBI used a large volume configuration. In this case, plasma pressure raised across whole plasma. At edge, higher temperature obtained growth width. However, effect FSTs significant small As at pedestal, ELM frequency...
The role of electron cyclotron resonance heating (ECRH) on the toroidal rotation velocity profile has been investigated in JT-60U tokamak device by separating effects change momentum transport, intrinsic pressure gradient, and ECRH. It is found that ECRH increases diffusivity convection velocity. also drives codirection (co) inside EC deposition radius counterdirection (ctr) outside radius. This ctr starts from propagates to edge region.
This paper reports the recent development of reversed shear plasmas with a high bootstrap current fraction (fBS) towards reactor relevant regime. The previous operation regime fBS is limited at q95 > 8 because low beta limit, whereas = 5–6 envisaged in DEMO reactor. In 2008 JT-60U experimental campaign, plasma was emphasized lower by developing large volume configuration close to conducting wall for stabilization. Thanks stabilization, exceeding no-wall limit are obtained ∼ 5.3. Though...
Abstract Quantitative validation studies of flux-tube gyrokinetic Vlasov simulations on ion and electron heat transport are carried out for the JT-60U tokamak experiment. The temperature gradient (ITG) and/or trapped modes (TEM) driven turbulent zonal flow generations investigated an L-mode plasma in local turbulence limit with a sufficiently small normalized thermal gyroradius weak mean radial electric fields. Nonlinear by GKV code successfully reproduce profiles energy fluxes core region....
A spontaneous transition phenomena between two states of a plasma with an internal transport barrier (ITB) is observed in the steady-state phase magnetic shear negative JT-60U tokamak. These ITB are characterized by different profiles second radial derivative ion temperature inside region (one has weak concave shape and other strong convex shape) degrees sharpness interfaces L mode region, which determined turbulence penetration into region.