A5040806312- Magnetic confinement fusion research
- Superconducting Materials and Applications
- Fusion materials and technologies
- Particle accelerators and beam dynamics
- Laser-Plasma Interactions and Diagnostics
- Nuclear reactor physics and engineering
- Ionosphere and magnetosphere dynamics
- Solar and Space Plasma Dynamics
- Nuclear Physics and Applications
- Particle Accelerators and Free-Electron Lasers
- Chalcogenide Semiconductor Thin Films
- Nuclear Materials and Properties
- High-Energy Particle Collisions Research
- Quantum Dots Synthesis And Properties
- Ranque-Hilsch vortex tube
- Strong Light-Matter Interactions
- Nuclear physics research studies
- Combustion and flame dynamics
- Digital Radiography and Breast Imaging
- Fluid Dynamics and Turbulent Flows
- Atomic and Subatomic Physics Research
- Spectroscopy and Laser Applications
- Metal and Thin Film Mechanics
- Radiation Detection and Scintillator Technologies
- Particle Dynamics in Fluid Flows
Kurchatov Institute
2009-2023
Budker Institute of Nuclear Physics
2020
Fusion Academy
2003
Fusion (United States)
2003
Institute of Atomic Energy
1973
The authors present the results of experimental studies on a discharge in Tokamak-6 device with specific instability whose appearance coincides sudden jump transverse energy plasma. It is shown that these regimes current carried by relatively small group runaway electrons energies 10 - 500 keV, while main plasma e ≃ 3 × 1012 cm−3 has low temperature (Te, Ti ∼ eV) and carries practically no current. Preionization working gas or introduction (∼ 2 – 3%) local inhomogeneity longitudinal magnetic...
The operational space (Ip − n) for long-pulse scenarios (Δtburn ∼ 1000 s, Q ⩾ 5) of ITER has been assessed by 1.5D core transport modelling with pedestal parameters predicted the EPED1 code a set codes under joint activity carried out Integrated Operational Scenario ITPA group. analyses include majority models (CDBM, GLF23, Bohm/gyroBohm (BgB), MMM7.1, MMM95, Weiland, scaling-based) presently used interpretation experiments and predictions. was modified to take into account boundary...
This paper describes the updates to and analysis of International Tokamak Physics Activity (ITPA) Global H-Mode Confinement Database version 3 (DB3) over period 1994–2004. data, for energy confinement time its controlling parameters, have now been collected from 18 machines different sizes shapes: ASDEX, ASDEX Upgrade, C-Mod, COMPASS-D, DIII-D, JET, JFT-2M, JT-60U, MAST, NSTX, PBX-M, PDX, START, T-10, TCV, TdeV, TFTR TUMAN-3M. The database contains 10382 data entries 3762 plasma discharges,...
The condition of the latest version ELMy H-mode database has been re-examined. It is shown that there bias in ordinary least squares regression for some variables. To address these shortcomings three different techniques are employed: (a) principal component regression, (b) an error variables technique and (c) selection a better conditioned dataset with fewer Scalings terms dimensionless physics variables, as well standard set engineering also derived. new scalings give very similar...
In order to prepare adequate current ramp-up and ramp-down scenarios for ITER, present experiments from various tokamaks have been analysed by means of integrated modelling in view determining relevant heat transport models these operation phases. A set empirical L-mode (namely, the Bohm–gyroBohm model scaling based with a specific fixed radial shape energy confinement time factors H96−L = 0.6 or HIPB98 0.4) has validated on multi-machine experimental dataset predicting li dynamics within...
We present integrated modelling of steady-state and hybrid scenarios for ITER parameters using several predictive transport codes. These employ models non-inductive current drive sources in conjunction with various theory-based semi-empirical models. In the simulation effort, are being evaluated a series cross-code code-experiment comparisons under ITER-relevant conditions. New benchmark evaluations from injection neutral beams (NBCD), electron cyclotron waves (ECCD) lower (LHCD) reported....
Experiments and simulations to achieve high values of plasma parameters at the Globus-M spherical tokamak (ST) moderate absolute auxiliary heating power (up 0.8 MW) specific 2–3 MW m −3 ) are described. Important distinguishing features low edge safety factor range, which is unusual for STs, 2.7 < q 5 small plasma–outer wall space (3–5 cm). High ion efficiency with neutral beam injection (NBI) was demonstrated. Results numerical simulation fast trajectories described generation during NBI...
Results of the simulation transport and radiation losses high-Z impurities (tungsten argon) in ITER reference operational scenarios are presented. The impurity dynamics was modelled by ZIMPUR code, a description which is This code integrated with ASTRA for background plasma behaviour modelling NCLASS to take into account neoclassical fluxes. Simulations show that flat density profiles thermal diffusion contributes core screening from heavy all considered scenarios. Thus, radiating layer...
The results of the experimental campaign on Globus-M (R = 0.36 m, a 24 m) devoted to investigating density limits and control are reported. experiments were performed at Btor 0.4 T, Ip 0.18–0.25 MA, q95 3.5–5 plasma vertical elongation, κ ∼ 1.5–1.7. achieved with gas puffing method in previous periods ohmic heating (OH) regime discussed. progress made OH scenario optimization helped approach Greenwald limit. Co-current neutral beam deuterium power range 0.45–0.6 MW energy 28–29 keV was...
The addition of high power, low aspect ratio data from the NSTX and MAST experiments has motivated a new investigation effect on confinement scaling. Various statistical methods, including those that incorporate estimates measurement error, have been applied to datasets constrained by standard set criteria in range κ Meff appropriate ITER operation. Development scalings using engineering parameters as predictor variables results ε-scaling coefficients 0.38 1.29; transformation these physics...
In preparation of ITER operation, large machines have replaced their wall and divertor material to W (ASDEX Upgrade) or a combination Be for the (JET). Operation in these has shown that influx can significant impact on discharge evolution, which made modelling this an urgent task. This paper reports such efforts. Maximum tolerable concentrations been determined various scenarios, both current ramp-up flat-top phase. Results two independent methods are presented, based codes ZIMPUR plus ASTRA...
Abstract Studying stationary regimes with high plasma confinement in a tokamak reactor technologies (TRT) [1] involves calculating the stability taking into account influence of current density profiles and pressure gradient pedestal near boundary. At same time, operating limits should be determined by parameters pedestal, which, particular, are set limit peeling–ballooning modes that trigger peripheral disruption edge localized (ELM). Using simulation quasi-equilibrium evolution ASTRA DINA...
ИССЛЕДОВАНИЕ УСЛОВИЙ ПОЛУЧЕНИЯ КВАЗИСТАЦИОНАРНЫХ РЕЖИМОВ В ТОКАМАКЕ Т-15МДВ.М.Леонов НИЦ «Курчатовский институт», Москва, Россия Выполнено исследование условий получения квазистационарных режимов в токамаке Т-15МД.Приведены результаты моделирования и оптимизации сценариев разрядов Т-15МД с полностью неиндуктивным поддержанием тока использованием систем генерации помощью нейтральной инжекции мощностью 6-8 МВт, ЭЦР-волн ~8 МВт ВЧ-волн до 7-8 МВт.Показано, что при несколько уменьшенной по...
In spherical tokamaks the conventional ICR plasma heating has a number of specific features and therefore requires additional investigations. For this aim modelling wave propagation absorption was performed by 1-D code developed at Ioffe institute. All possible mechanisms RF (cyclotron fundamental second harmonics, TTMP, Landau) were taken into account. The calculations demonstrated possibility effective power both ions electrons in broad range parameters (including relative hydrogen...
Abstract The neutral beam injection (NBI) experiments on the Globus-M and TUMAN3-M tokamaks in Ioffe Institute are prepared. In order to maximize absorbed power reduce ion orbit losses transport modeling of planed was performed. On base target plasma parameters as well experiment geometry were chosen. It is shown that at density 2 × 1019 m−3 energy ∼25 keV "shine-through" first-orbit negligible. NBI 0.6-1.0 MW allow increase ratio pressure magnetic field - β up critical values (∼20-30% for...
This paper presents the main parameters and design of proposed T-15MD tokamak. The installation is meant for demonstration tokamak two-component operating mode steady state operation problems-solving with a plasma current drive (CD) at level about 1 MA. Injection hydrogen neutral beams power up to 8 MW chosen as method noninductive CD. For an electron temperature increase it supposed use ECH 6 frequency 110 GHz. Parameters ion source IVIS KS 3 which under development characteristics NB...
The objective of the present paper is to investigate vertical stability plasma column in project T-15M tokamak. It has been shown that a passive stabilizing structure consisting vacuum vessel and two (upper lower) coils capable providing column.
Properties of toroidal Alfvén eigenmodes (TAEs), driven by neutral beam injection (NBI) hot ions, are described for the tokamak T-15 under construction in Kurchatov Institute to test a possible influence on and plasma particle losses. The baseline scenario with 10-s flat-top 2 MA current stage, 6-MW NBI plus 6 MW electron cyclotron resonance (ECR) heating is computed ASTRA code. spatial structure frequencies different TAE modes indexes n = 8 have been obtained ideal magnetohydrodynamic KINX...