Search

Issues of numerical simulation of an experiment on compression and heating of a target in a magnetic field are discussed. It is found that the applied magnetic field predominantly increases the plasma lifetime and plasma jet characteristics (velocity, Mach number, density, etc.). An analysis of the effects of the application of an external magnetic field on the behavior of plasma-driven guns (plasma jets) and laser-driven systems (laser beams) is carried out. Thermodynamic questions in simulation of experiments on magnetic inertial synthesis are touched upon.

The mathematical model and the results of computer simulation of the processes of compression, heating, and energy release in a target under the hybrid influence of a system of pulsed plasma jets and intense laser radiation in magnetic inertial thermonuclear fusion are presented. The hybrid effects of intense energy flows on a single-layer cylindrical target are compared in the experimental and simulation conditions. The main radiation magnetic and gas dynamic parameters of the compressed and heated target plasma are evaluated as well.

The basic properties of the plasma of capillary discharges are discussed. A mathematical simulation of the interaction of pulsed plasma jets generated by a capillary discharge at atmospheric pressure is presented.

A mathematical model is presented that describes the effect of intense laser pulses of a rectangular shape on a two-layer cylindrical target. The fluxes of the intrinsic plasma radiation for seven spectral ranges are calculated as a function of the radial target coordinate. Spatial distributions of the total flux of the plasma radiation are presented.

A mathematical model for the compression process of a cylindrically symmetric thermonuclear target is presented. A numerical method of an increased accuracy order is considered, which is used to calculate the basic physical processes that occur in target plasma exposed to an external magnetic field.

This research is devoted to the calculation and theoretical analysis of physical processes in the powerful electric discharge sources of UV radiation and shock waves with required and controlled technical and physical characteristics. Based on the calculations, the processes of converting the initially stored electromagnetic energy into internal, kinetic, magnetic and radiation energy formed in the electro-discharge plasma sources of plasma formation were studied, and the interactions of discharged plasma and its radiation with matter in different aggregate states were also studied. All the main magneto-plasma dynamic and radiative parameters of plasma formation in the electric discharge sources of UV radiation and shock waves are obtained.

A combined scheme of hot plasma confinement is proposed, and laser and plasma-based methods for generating a megagauss field during the implosion of a magnetized target are described that allow the development of new high-density plasma sources for materials science experiments and advanced areas of power engineering. A procedure for numerical calculation of the physical processes involved in the target plasma in an external magnetic field is presented.

A capillary discharge with an evaporating wall, namely system of pulsed plasma jets is considered. The structure of an underexpanded supersonic jet that expires from the plasma channel of the capillary discharge with an evaporating wall is investigated. The turbulent viscosity and thermal conductivity coefficients are calculated using the equations of the Coakley model. Numerical simulation is performed and spatial distributions of plasma pressure, and temperature for an array of three pulsed plasma jets at different moments of time are obtained.

Results of experiments on the formation of a compact toroidal magnetic configuration at the Compact Toroid Challenge setup are presented. The experiments were primarily aimed at studying particular formation stages. Two series of experiments, with and without an auxiliary capacitor bank, were conducted. The magnetic field was measured, its time evolution and spatial distribution over the chamber volume were determined, and its influence on the formation regimes was investigated.

The present work reports on compact toroid hydrogen plasma creation by means of a specially designed discharge system and results of magnetic fields introduction. Experiments in the compact toroid challenge (CTC) device at P.N. Lebedev Physical Institute (FIAN) have been conducted since 2005. The CTC device differs from the conventional theta-pinch formation in the use of an axial current for enhanced efficiency. We have used a novel technique to maximize the flux linked to the plasma. The purpose of this method is to increase the energy input into the plasma and the level of trapped magnetic flux using an additional toroidal magnetic field. A study of compact torus formation with axial and toroidal currents was done and a new method is proposed and implemented.

Magneto-inertial fusion (MIF) is an original technique of inertial thermonuclear fusion, where spherical and cylindrical gas or plasma configurations are compressed under the action of an external magnetic field. We present a brief review of recent data on laser- and plasma jet-driven MIF systems and possible ways they can be applied. This work also presents problems of and prospects for the application of such approaches.

The work is devoted to theoretical calculations of compression and energy release processes in the target, which is used in a magnetoinertial fusion (MIF) concept consisting of pulsed jets and intense laser radiation. A numerical technique, describing plasma-physical processes occurring in MIF system, is developed. The results of the calculation of the combined effects (pulsed jets and laser radiation acting on a cylindrical target in the end and perpendicular directions) of intense energy flows on a single-layer cylindrical target are presented. All the main plasma dynamic and radiative parameters of the compressed target plasma were found.

This paper deals with the analysis of the possible use of magneto-inertial fusion (MIF) to create a neutron source. We consider the configuration of the target in the form of an axially symmetric m...

The physical and mathematical model and numerical method for calculation of the main parameters of plasma during the implosion of a magnetized target in magneto-inertial fusion (MIF)1–5 are developed.

We analyzed the energy balance of a fusion system based on an axially symmetrical open trap. In the considered system, the injection of high-energy (fast) particles is the main source of plasma external heating. Simulation of physical kinetics of the injected particles is based on the numerical solution of the Fokker-Planck equation taking into account scattering into the domain of losses and participation in the fusion reactions. Despite the considerable energy losses of the injected particles when leaving the trap due to the angular scattering, the considered system is sufficiently effective to be used as a source of neutrals for the hybrid (fusion-fission) reactor. The principle possibility of achieving a power amplification of Q pl ≈ 1 in plasma was demonstrated in operation modes with high neutron yield.

As applied to a tokomak, a magnetic trap for confinement of a plasma with an inverted field or a magnetic field reversed configuration (FRC) is one of the most promising alternatives of the systems with high β. A brief review of the latest data on FRC and potential directions of using such configurations in addition to energy generation in thermonuclear reactors (TNRs) is proposed.

The paper is devoted to the principles of magneto-inertial fusion and laser-plasma methods of generation of a Megagauss field during spherical implosion of a magnetized target. A model based on a magnetic confinement system, namely, a cusp configuration with inertial compression of the target by a laser driver, is developed. The dynamics of plasma in a cusp compressed under the effect of laser beams is precalculated. Analytical and numerical estimates of the particle number and magnetic field intensity during magneto-inertial plasma compression are obtained. The problems of irradiation of a spherically closed volume by a high-energy laser pulse are discussed.

Magneto-inertial fusion (MIF) is based on both magnetic and inertial confinement. An embedded magnetic field is compressed along with the target plasma to achieve magnetic insulation and fusion condition. Several magnetic systems for plasma confinement may be used for laser-driven (LD) and plasma jet driven (PJ) magnetic flux compression. Estimations show the possibility in principle to realize regimes of PJMIF system with a plasma gain factor Q > 10.

The compact torus/toroid (CT) as future fusion reactor is presented. The field reversed configuration (FRC) is alternative thermonuclear scheme with properties of compact tori as both open and closed systems. By plasma confinement method field reversed configuration is closed magnetic trap. Mathematical model of plasma core in the fusion reactor is shown. Power balance for the FRC confinement chamber is calculated. The formula for bremsstrahlung more accurate in the temperature range of advanced fuel is presented. D- 3 He- 6 Li fuel cycle is proposed and reactor schemes are discussed.

Innovative schemes of compression and heating of targets in the concept of magneto-inertial fusion (MIF) are proposed. "Standard" MIF version assumed target plasma and magnetic flux compression by high-speed plasma jets (plasma liner)1 or/and quasisymmetric laser-driven implosion of magnetized target2. The maximum value of magnetic field in the "standard" version can be obtained in the target volume.

Field reversed configurations (FRC), 1,2,3 as mirror machines have been developed as simple plasma confinement systems. FRC formed by reversing of magnetic field and reconnection and sustained by plasma current. Several mirrors may be linked together with solenoids - tandem mirrors (TM), end losses in the axisymmetric tandem mirror are reduced by ambipolar trapping - ambipolar trap (AT). Power balance of deuterium - helium-3 (D- 3 He) plasma in a prolate FRC power plant is compared with the power balance for a central cell of D- 3 He tandem mirror reactor (ambipolar trap). Deuterium - tritium (D-T) ITER 4 , kinetically stabilized tandem mirror (KSTM)5 and D- 3 He FRC5 parameters are demonstrated.

Gradient-drift (collisionless Simon-Hoh) instability is a robust instability often considered to be important for Hall plasma discharges supported by the electron current due to the E × B drift. Most of the previous studies of this mode were based on the local approximation. Here, we consider the nonlocal model which takes into account the electron inertia as well as the effects of the entire profiles of plasma parameters such as the electric, magnetic fields, and plasma density. Contrary to local models, nonlocal analysis predicts multiple unstable modes, which exist in the regions, where local instability criteria are not satisfied. This is especially pronounced for the long wavelength modes which provide larger contribution to the anomalous transport.

The high fusion power density resulting from high beta (the ratio of the plasma to magnetic energy density) and natural divertor make the field-reversed configuration (FRC) a prime candidate for fusion reactor other than tokamak, the so-called alternate concept. Brief review of the simple compact system with natural advantages and reactor potential is given. Theoretical and experimental results over the last seven years are discussed.

Field-Reversed Configuration (FRC) [1] and Gas-Dynamic Tr ap (GDT) [2] represent compact system, which is a special magnetic geometry for plasma confinement. Theoretical and experimental study of gas-dynamic regimes with high energy content is carried out. The approach to a high beta (b is the ratio of plasma pressure to magnetic pressure) magnetic systems assumed different regimes of plasma with beta > 0.5 that is proper to compact devices such as tori and mirror traps. Both FRC and GDT traps are axial symmetric configurations, has open field lines and poloidal magnetic field only. Last experimental results on GDT have shown the po ssibility to build the stationary system with high beta. Analysis of the global energy and particle balance together with the Monte-Carlo equilibrium modelling allowed to conclude that two-component plasma confined in a steady-state regime. The characteristic plasma lifetimes are 4 to 5 times less then the experiment duration. A peripheral gas-puff near the mirror region enabled to maintain the radial profile of background plasma during the all neutral beam injection (NBI) pulse. This report is focused mainly on ambipolar effect and the po ssibility of further increasing the fast ion energy content and β. Improved gas-dynamic regimes in high pressure magnetic discharges and microinstabilities arising are described. Synthesized hot ion plasmoid (SHIP) experiment in the compact mirror section attached to the GDT central cell and the scheme of compact tori (FRC formation) for the compact mirror cell of GDT device are presented. Fusion prospects (reactor, neutron source, material studies) of such systems with high-energy (fast) particles [3, 4] and hybrid FRC + GDT scheme proposed by author from Bauman Moscow State Technical University (BMSTU) are discussed. NOMENCLATURE AND ABBREVIATION b = ratio of plasma pressure to magnetic pressure τE = energy lifetime

We report here our results on the formation of a plasma configuration with the generic name of compact toroid (CT). A method of compact toroid formation to confine, heat and compress a plasma is investigated. Formation of a compact torus using an additional toroidal magnetic field helps to increase the plasma current to a maintainable level of the original magnetic field. We design the Compact Toroid Challenge (CTC) experiment in order to improve the magnetic flux trapping during field reversal in the formation of a compact toroid. The level of the magnetic field immersed in the plasma about 70% of the primary field is achieved. The CTC device and scheme of high level capturing of magnetic flux are presented.

Various possibilities of improving of tandem mirror systems are considered. Methods of reducing significant disadvantage of open system - intensive emission interaction between plasma and chamber wall surface and possibility of decreasing of electrostatic barrier value are considered. Creating so-called double tandem mirror system is suggested to obtain mirror based confinement system without magnetic force lines, piercing chamber wall surface. Besides, principle of realising other suggested method of protecting of plasma - magnetic insulation is presented. It is shown, that magnetic insulation in mirror based fusion reactor can give significant protective effect.

A numerical model of ion kinetics is considered for the axially symmetrical magnetic trap. The trap contains warm Maxwellian plasma and strongly non-Maxwellian high-energy (fast) ions. The steady-s...