Abstract The proposing Method unlike to using now others comprises in usage for plasma creation and its further ignition the created in-situ halo-layer of high-energetic particles to the puffed gas. For realization of Method the following procedures should be performed consistently and corresponding hardware should be included in toroidal fusion reactor: In-situ creation of halo-layer: orthogonally to equatorial plane of toroidal vacuum chamber to create generally the time-dependent magnetic field (bending field) penetrating only its curvilinear segments, to apply axial (toroidal) magnetic field only in the regions located remotely from injection points, along the axis of toroidal vacuum chamber to inject 3 different kinds of pulse high current particle beams (two ions’ – reacting components and one – electron’s) with such a parity of particles’ kinetic energies allowing them the capability of moving in a given bending magnetic field on a common equilibrium orbit (gyroradiuses (rg=p/qB) of all 3 spices are equal) in such a manner that faster ion beam passes through the moving at the same direction slower ion beam with sufficient for nuclear fusion collision energy and the relativistic electron beam moving oppositely to ions thus allowing to combined beam the self-focusing capability, to apply axial (toroidal) accelerating electric field compensating the occurring together with fusion two effects: tendency of alignment of velocities of reacting particles and also electrons’ energy losses via Bremsstrahlung. Number density up to 1024 m-3 and even higher is achievable in combined beam and as result of fusion the high energetic fusion products are produced, from which neutrons escape reactor while charged particles form halo-layer. For creation of plasma and its ignition at once after injection: from the walls with the help of corresponding valves to puff into the vacuum chamber the gas consisting the fuel components. And already being there halolayer ionizes that gas and then generates the current similarly to that how current is driven by beam/beams of neutrals in modern TOKAMAKs. in regions being free from axial magnetic field to apply such a field at once after the end of injection. The Method allows the reliable ignition of plasma in all kinds of toroidal fusion reactors. Claims 1. The Method for creation of plasma and ignition of self-sufficient reaction in toroidal fusion reactors, the Method comprising the following procedures that should be performed consistently and corresponding hardware should be included in toroidal fusion reactor: 1. Orthogonally to equatorial plane of toroidal vacuum chamber to create generally the time-dependent magnetic field (bending field) penetrating only its curvilinear segments (as generally the toroidal chamber may also have rectilinear segments – racetracks). 2. To apply axial (toroidal) magnetic field in the regions located remotely from injection points 3. Along the axis of toroidal vacuum chamber to inject 3 (three) different kinds of pulse high current particle beams (two ions’ – reacting components and one – electron’s) with a such a parity of particles’ kinetic energies and corresponding momentums (depending on particles’ mass-to-charge ratio) allowing them the capability of moving in a given bending magnetic field on a common equilibrium orbit in such a manner that faster ion beam passes through the moving at the same direction slower ion beam with sufficient for nuclear fusion collision energy and the relativistic electron beam moving oppositely to ions thus allowing to combined beam the self-focusing (pinch) capability thanks to the only partial compensation of reacting ions’ positive space charge and also to the magnetic attraction of all 3 (three) unidirectional currents creating self-magnetic field (poloidal field), 4. To apply axial (toroidal) accelerating electric field compensating the occurring together with fusion two effects: tendency of alignment of velocities of reacting particles and also energy losses of electrons via Bremsstrahlung. (Similarly to how current driving field is induced e.g. in TOKAMAKs). For preservation of comparatively constant value of equilibrium orbit’s radius the action accelerating field should be coordinated with increase in intensity of bending magnetic field. Such a requirement is automatically satisfied in betatrons without any external regulation while in synchrotrons external regulation is used. So, even in case of necessity of regulation that is achievable and would not be a big problem. 5. To puff the gas consisting the fusion fuel components from the walls into the vacuum chamber until filling of chamber to desired pressure. Halo-layer will ionize the gas and then will generate the current similarly to that how current is generated in so called Advanced TOKAMAKs (H-mode – beam driven current) 6. At once after injection in regions free from axial magnetic field to apply such a field similar to that is applied in TOKAMAK reactors 2. The procedure and corresponding hardware of claim 1, the bending magnetic field directed orthogonally to equatorial plane of toroidal vacuum chamber (vertically) penetrating only its curvilinear segments. As a rule the vacuum chamber of toroidal fusion reactors has a round central axis but generally round segments can alternate with the rectilinear segments (racetracks). As the Method is proposing injection along the axis of high current beams, presence of racetracks would be preferable as they provide easier injection. Such racetracks have been used in first Stellarators. Also they widely used in high energy particle accelerators for example racetrack FFAG betatron for Muon Fabric (Brookhaven National Laboratory) or Induction Synchrotron (All-ion Accelerator) developing now by KEK (High Energy Accelerator Research Organization) And it is proposed to create orthogonally to equatorial plane of vacuum chamber the bending magnetic field penetrating only its curvilinear segments. Such a field may be created by dipole magnets like to how similar purpose fields are created in synchrotrons or by betatron type magnet systems. The order of initial value of that field would be 0.1-0.4T. Then in the course of acceleration field’s induction should be increased correspondently to instant momentums of maintaining particles, thus keeping comparatively constant equilibrium radius. 3. The procedure and corresponding hardware of claim 2, to apply axial (toroidal) magnetic field only in the regions located remotely from injection points Periodic axial magnetic field is needed for avoiding or slowing down of instabilities (e.g. two-stream instability) As it is shown in number of papers [e.g. 9], such a field dramatically expands stability area. At the injection moment beams injection points should be free from influence of that field. 4. The procedure and corresponding hardware of claim 3, to inject into the common axis (axis of vacuum chamber) 3 (three) pulse high current beams. It is offered to inject two beams of particles of reacting components and to direct them along the same orbit and at the same direction but with different coherent motion velocities. So, one faster ion beam should transit (pass) through another slower ion beam and their relative velocity should be sufficient for providing to reacting nuclei enough collision energy required for fusion (enough energy for Coulomb barrier overcoming). For achievement of sufficient intensity of nuclear fusion the focusing of reacting beams is necessary. For this purpose it is offered to direct the relativistic electrons beam along the same orbit but towards (oppositely) to reacting particles beams. This relativistic electron beam should compensate the positive space charge only partially and at the same time thanks to the magnetic attraction of combined three beams (three unidirectional currents) will compress the whole system in radial direction (pinch-effect). In fact pinch-effect will be provided thanks to the circumstance that in frame of reference connected with ions combined beam will charged negatively and for frame of reference connected with electrons – positively. In the first approximation (not taking into consideration self-fields and influence of walls) the condition for beams for moving along the same equilibrium orbit is equality of gyroradiuses of particles. Gyroradius can be calculated by the formula: rg=p/qB (1), Where: rg – gyroradius of particle q – charge B – induction of bending field And equality of gyroradiuses for equally charged particles (e.g. deuterium, tritium and electron) means that their coherent motion momentums should be equal. And e.g. for: Deuterium – 450keV Tritium – 300keV Electron – 40.6MeV all momentums are equal to ~2.2*10-20 kg*m/s and at Bb=0.1T rg=~1.4m Deutrons 450keV and Tritons 300keV moving along the same axis at the same direction have center-of-mass collision energy ~30keV. Such an energy provides rather high fusion cross section equal to ~1barn G.I.Budker  says about achievability of order of magnitude of number density in such beams of 1026m-3 and even higher and beam’s radius of fractions of mm. Generally radial dimension of combined beam is a function of circulating currents, positive space charge neutralization level, coherent velocities of ions, relativistic factor γe and temperature. And varying with electron current for a given ion currents we can easily control the radius of combined beam. For a given above sample of particles’ energies: γe=80.5 (relativistic factor of electrons in fixed frame of reference) γt=81.6 (relativistic factor of electrons in frame of reference connected with tritium) γd=82.2 (relativistic factor of electrons in frame of reference connected with deuterium) And if nd=nt=ni/2, condition of pinch (excess of magnetic attraction forces on space charge repulse forces) will be: ne>1/3355ni So, the combined beam may be dramatically non-neutral and nevertheless suffering pinching. And this circumstance would be salutary for energy balance. Injection challenge Injection into vacuum chamber of very high current beams is a challenge. As the currents of thousands Amperes order for electron beam and tens/hundred thousand Amperes for ions are required. And before neutralization such beams are space charge dominated. But induction electron accelerators (Induction Linacs) produce rather high quality beams (energy spread <1%) and, so, having narrow phase volume (space), radius of vacuum chamber would have 0.5-2m order, while electron beam’s radius before injection – ~0.15m and electrons will be high relativistic 40.6MeV (γe=80.5, repulse forces reduce by factor of 1/γ2). And commonly the injection of intense relativistic electron beams is well developed in number of laboratories  Fig. 1 And if we would inject firstly the electron beam and that then will totally fill the whole circumference (along axis) of chamber, the rather deep potential well for positively charged particles will be created, the depth of which is equal to : W=ve(1+2ln(R/Re)mec2 (2), Where: ve – Budker’s parameter ve = Ne2/m0c2 N-linear density (for Ie=4kA ve=0.235) R – radius of vacuum chamber Re – radius of electron beam And for Ie=4kA, R=0.75m, Re=0.113m (je=10A/cm2) W=1.123*mec2=574keV And 574keV is rather enough depth for effective injecting into the same space ions producing by ion diodes even despite the fact that they have high energy spread and, so, big phase space. Energies of ions: Deuterium – 450keV Tritium – 300keV Injectors For electron injection it is more suitable to use Induction Linear Accelerators (Induction Linacs) producing: currents of kilo-amperes orders (10000 A by ATA accelerator ) particles energies up to 50 MeV (with the spread <1% ) pulse duration – 50 ns -1.2 μs These parameters allow the effective injection of electron beams into the chamber with reasonable radial dimension (up to 2 m for modern TOKAMAKs) For ions – the Ion Diodes or combination of Ion Diodes with additional Inductive Voltage Adders would be more suitable. As: Ion Diodes produce currents up to mega-Amperes orders Energies of particles – up to several MeV (several hundreds keV are more common) Pulse duration – 50 ns – several μs But energy spread produced by Ion Diodes is rather high and, so, ion beams occupy big phase space. From the one side wide spread would be useful for avoiding of some types of instabilities (e.g. two-stream instability) but from another – it makes more difficulties for injections. But as has been showed above, if electron beam would be injected before ions, that creates enough potential well for further injection of ions. Combination of Ion Diodes with Inductive Voltage Adders also dramatically reduces spread. 5. The procedure and corresponding hardware of claim 4, to apply the axial (toroidal) accelerating electric field. If considering elastic collision of two particles moving at the same direction with different velocities, faster moving particle will transfer some momentum (and corresponding energy) to slower one, thus accelerating that and decelerating itself. For the case when slower particle has bigger mass , : ΔE=γ2β2mc2 Θ/2 (3) Δp= ΔE/v, Where: γ – relativistic factor of faster particle in the frame connected with slower β – vrelative/c (vrelative - relative velocity of two particles) m – mass of faster particle Θ – scattering angle And for interesting for us case average energy loss of faster moving Deuteron per each elastic collision (scattering event): ΔE=10.9eV (corresponds to Θ=0.85 deg) And taking into account that ratio between scattering and fusion cross sections differs on about 4 orders of magnitude, we should wait that: Deuteron 450keV decelerates to ~340keV Triton 300keV accelerates to ~410keV before they fuse. Naturally, mentioned above kinetic energies do not provide collision energy sufficient for fusion (not less than 10keV in center-of-mass frame) And for this reason it is offered to apply along the axis the electric field accelerating particles in a manner similar to TOKAMAK in which that firstly breakdowns gas, ionizing that and drives the current. TOKAMAK needs comparatively high intensity of electric field initially (up to 100 V/m when gas breakdown goes) but then by growth of plasma conductivity required intensity should be much lower (typical value of loop voltage – from fraction of Volt to 1 Volt which corresponds to 0.5V/m of intensity and even lower). Nevertheless due to high conductivity of hot plasma this voltage drives mega-Amperes order current. For estimation of required intensity of electric field let us admit that: number density of pinched combined beam – 1023 m-3 required confinement time in this case – 10-3 sec And in this time the electric field of 50 V/m intensity will give to deuterium additional energy ~387keV and to tritium – ~240keV And as result after the lapse of offered cycle will have: Deuteron 450keV accelerates to ~727keV Triton 300keV accelerates to ~650keV that provides collision energy in center-of-mass frame 21.6keV (quite sufficient for fusion) Here we should also to notice that particles from the beginning having equal gyroradiuses as result of described phenomena gain the certain mismatch from equilibrium momentums (about 18%) but also we have described that attraction of three unidirectional currents creates enough potential well confining them together. According data provided by Stallatron (high current Betatron with additional Stellarator type windings) developers  such a scheme allows mismatch of energies up to 50% from equilibrium. Requirements on axial electric field For creation of axial electric field if we would use iron core transformer made of permendur (saturation limit 2.5 T), circumference of toroidal chamber L=15 m, inner area available for core S=20 m2 , mentioned above electric field E=50 V/m intensity can be kept in: Bmin= - 2.4 T Bmax= 2.4 T Loop voltage : Vloop=LE t= S(Bmax-Bmin)/LE=0.128 sec = 128 milliseconds So, after 1 millisecond there is enough reserve to pass then on lower intensity (~0.5 V/m) using in TOKAMAK mode with hot plasma. 6. The procedure and corresponding hardware of claim 5, at once after injection from the walls with the help of corresponding valves to puff into the vacuum chamber the gas consisting the fusion fuel components until filling the chamber up to desired pressure. It is offered to use several gas-puff valves divided along circumference of reactor in regular intervals and to open them at certain moment puffing the certain quantity of gas: e.g. equal (by volume) mix of deuterium and tritium gases. Already being there halo-layer will ionize that gas and then generate the current similarly to that how current is generated in so called Advanced TOKAMAKs (Hmode – beam driven current) and rise the temperature until thermonuclear temperature (higher than 10keV) As the energy of halo-layer is in more convenient for energy transfer form – fast moving ions, energy of those ions 3.5MeV + energy corresponding to velocity of center-of-mass frame (2.63*106 m/s in considering here case) and that energy will be absorbed by cold gas within a few milliseconds increasing its temperature to desired value (10 keV and higher) 7. The procedure and corresponding hardware of claim 6, at once after injection in regions free from axial magnetic field to apply such a field similar to that is applied in TOKAMAK reactors Injection of charged particles across force lines of magnetic field is impossible. So, initially there should not be an axial/toroidal magnetic field at least near injection points. But axial field is necessary for further confinement of hot plasma (that is the one of the main components of TOKAMAK confinement concept) And there are some methods of fast creation of axial fields and then keeping them at constant value during certain period. For example to use two coils: so called ―fast coil‖ being lower in diameter, having lower inductance but conducting very high current. Such a coil may create short pulse magnetic field, while larger but more inductive coil’s field will rise slower but for longer time period till the end of necessity of confinement.