RU2056649C1 - Controlled thermonuclear fusion process and controlled thermonuclear reactor implementing it - Google Patents

Abstract

FIELD: power engineering, nuclear physics, thermonuclear fusion. SUBSTANCE: fuel mixture is doped with substances possessing large area of their interaction with neutrons, positive energy release, and incorporating, in addition to other products of reaction, tritium, such as ⁶Li, ⁷Li, ³He. Neutrons formed in thermonuclear fusion reactions are focused onto fuel mixture, ³He and T nuclei are separated from products of reaction and returned to source fuel mixture. Reactor has working chamber with plasma forming and holding unit, energy conversion device, fuel mixture treatment and introduction unit. Plasma forming unit is provided with device for forming and focusing thermal neutron flux with neutron source. Fuel mixture introduction unit faces focus area of device for forming and focusing thermal neutron flux. Separating unit for products of reaction is connected to treatment unit and to fuel mixture introduction unit. Coolant flows through working chamber of reactor and through separating unit for products of reaction. EFFECT: improved reliability of nuclear fusion control. 9 cl, 9 dwg, 1 tbl

Description

 The invention relates to nuclear physics, in particular to the physics of fusion processes.

A known method of thermonuclear fusion using deuterium (D) and tritium (T) as fuel, including the preparation, heating, and subsequent confinement of heated thermonuclear plasma, is implemented in an explosive device (in a thermonuclear bomb) containing a fuel mixture comprising deuterium (D) , tritium (T), fission-based neutron source, neutron-reflecting structure and explosive-type plasma confinement device [1] The initial fuel mixture contains lithium deuteride. In this method, fast primary neutrons that are formed in fission reactions of heavy nuclei are concentrated to interact with lithium nuclei contained in the initial mixture, and the mixture is heated in the course of ongoing exothermic reactions. The resulting fast tritium nuclei interact with deuterium and tritium in the initial mixture and heat it up to the temperatures of nuclear interaction in the substance of the fuel mixture, after which pure thermonuclear deuterium-deuterium (D + D) and deuterium-tritium (D + T) reactions begin in the device. Secondary neutrons formed in the process also interact with lithium (Li) nuclei and secondary neutron-interacting helium-3 ( ³ He) nuclei formed in thermonuclear reactions. As a result, fast nuclei are formed, including tritium nuclei involved in the main reactions. For concentration, fast primary neutrons are reflected from the screen, which is external to the reaction region, and returned to it. The plasma confinement is carried out using an external explosive device. The retention time is characterized by the duration of the explosion, and with increasing retention time and neutron density in the heating region of the mixture, the fuel burnup efficiency and the energy efficiency of the device increase.

 This method of thermonuclear fusion of light nuclei using fast neutrons is not stationary and fundamentally not controlled.

A known method of controlled thermonuclear fusion, adopted as a prototype [2] Its essence lies in the fact that the prepared fuel mixture, including deuterium (D) and tritium (T), is introduced into the heating region and heated to the temperature of nuclear interaction in the plasma T _i ≥ 10 KeV external devices, including heating by a non-stationary magnetic field, then hold the plasma by the action of a magnetic field and transform the released energy.

 This method of controlled thermonuclear fusion is energetically inefficient primarily at the stage of fuel heating. The method can be implemented in single and extremely expensive installations, since the energy efficiency of the method depends on the size of the retention area and the total power of the device.

 Known controlled thermonuclear reactor for implementing this method [3] It contains a working chamber with a node for the formation and confinement of plasma and a plasma confinement region, a preparation unit and an inlet for the fuel mixture, a device for separating reaction products and a device for energy-energy conversion.

 The disadvantage of this reactor is its energy inefficiency, which is associated with its design features. In this reactor, the plasma forming unit heats the fuel mixture and forms the plasma with energy carriers external to the plasma, and therefore, during the burnout of the mixture, the energy invested in the heating must be replaced. This does not allow, until critical parameters for plasma characteristics and operation mode are reached, to have an energy-efficient device, and the strong dependence of these parameters on the characteristic dimensions of the device and the energy input and therefore the high cost do not allow it to be energy-efficient in practice.

 The problem solved by the invention is to create an energy-efficient method of controlled thermonuclear fusion and a controlled thermonuclear reactor for its implementation.

 The solution to this problem is due to the following technical results: the self-sufficiency of the method according to the isotopes used in it, the energy efficiency of the method at all stages of heating and burning of the fuel mixture; beneficial use of neutrons.

 Additional technical results are an increase in the efficiency of removal of energy released in the reactor, an increase in the efficiency of energy conversion, a decrease in thermal loads on the "first wall" of the reactor.

 These technical results are achieved by the fact that, according to the invention, substances interacting with neutrons are added to the initial fuel mixture by the controlled thermonuclear fusion method, including preparing, introducing and heating a fuel mixture containing deuterium and tritium to nuclear interaction temperatures, plasma confinement and energy conversion. with positive energy release and forming tritium in the course of fusion reactions, thermalize the neutrons formed in fusion reactions and focus them focal area on the fuel mixture under heating, and then after hot fusion plasma containment and converting the energy released is separated helium-3 and tritium nuclei of reaction products in plasma and return them to the original fuel mixture.

A possible implementation of the method, when the temperature in the plasma is maintained such that the following relationship between the parameters characterizing the plasma:
n _D · <σ · V> _DD ≥ n _T · <σ · V> _DT , where n _{D is the} density of deuterium in the plasma;
n _T plasma tritium density;
<σ · V> _{DD are the} averaged interaction cross sections and the ion velocity in DD reactions in the plasma;
<σ · V> _{DT are the} averaged interaction cross sections and the ion velocity in the DT reactions in the plasma.

 A possible implementation of the method is when the fuel mixture is carried out and introduced in the form of solid targets, the neutrons are focused in the focal region at a distance from its center such that the distribution of neutron density in the focal region has a minimum at the center, and the nearest maxima lie at a distance larger than the size of the targets .

 The essence of the proposed controlled nuclear fusion reactor is that in a reactor that contains a working chamber with a plasma forming and holding unit and a plasma holding area, a preparation unit and a fuel mixture input unit, an energy removal-energy conversion device, a reaction product separation device, according to the invention, an assembly of plasma formation is equipped with a thermalization device and the formation of a directed neutron flux with a focal region, the fuel mixture input unit is oriented to the focal region of the device oystva thermalization and formation of directional flux of neutrons, the reaction products separation assembly is connected to the node preparing the fuel mixture.

 A reactor embodiment is possible, characterized in that the energy removal-energy conversion device comprises a coolant circuit with channels of a coolant circuit, which is connected to a working chamber and a separation unit for reaction products.

 A reactor embodiment is possible, characterized in that the channels of the coolant circuit at the entrance to the working chamber of the reactor have a tangential slope relative to the plasma confinement region.

 A possible implementation of the reactor, characterized in that the site of the formation and retention of the plasma is made in the form of a magnetic trap.

 A reactor implementation option is possible, characterized in that the plasma confinement unit is made in the form of an open magnetic trap, part of which has the form of a magnetic nozzle connected to an energy extraction-energy conversion device.

 A possible implementation of the reactor, characterized in that the magnetic trap contains magnetic coils that are connected to a device for energy extraction-energy conversion.

In FIG. 1 shows a flow chart of a method of controlled thermonuclear fusion; in FIG. 2 shows a cycle of the method, closed by T and ³ He; in FIG. 3 controlled thermonuclear reactor; in FIG. 4 controlled thermonuclear reactor based on an open magnetic trap with a one-sided “bottle” field configuration; in FIG. 5 controlled thermonuclear reactor based on a closed corrugated torus magnetic trap with axial plasma heating; in FIG. 6 controlled thermonuclear reactor based on a closed trap "tormac" with peripheral plasma heating; in FIG. 7 controlled thermonuclear reactor with spherical symmetry of a thermalization device and the formation of a directed neutron flux; in FIG. 8 is a graph of the spatial distribution of neutrons in the focus of a thermalization device and the formation of a directed neutron flux of a reactor; in FIG. 9 is a graph of neutron flux versus time at the focus of a thermalization device and the formation of a directed neutron flux.

 The proposed reactor contains a working chamber 1, a node 2 for forming and holding a plasma, a node 3 for preparing a fuel mixture, a node 4 for introducing a fuel mixture, a device 5 for energy extraction and energy conversion, a device 6 for separating reaction products, a device 7 for thermalizing and forming a neutron flux, a focal region 8 of the device thermalization and formation of a neutron flux, an external source of 9 neutrons, a coolant circuit 10, an additional focal region 11, a plasma confinement region 12.

 A working (reaction) chamber 1 is placed inside the reactor pressure vessel, which is covered by the device 7 for thermalization and formation of a neutron flux. The focal areas 8 of the device for thermalization and formation of a neutron flux are located inside the working chamber 1 of the reactor. Through the device 7 for thermalization and formation of a directed neutron flux and the working chamber 1 pass the channels of the fuel mixture input unit 4, which are connected to the fuel mixture preparation unit 3, and the reaction product separation unit 6, which is connected to the fuel mixture preparation unit 3 and its input unit 4 . The channels of the fuel mixture input unit 4 and the reaction product separation unit 6 can be combined with the channels of the coolant circuit 10. The coolant circuit 10 passes through a working chamber 1 with a plasma confinement region 12, a reaction product separation device 6 and an energy removal-energy conversion device 5. The node 2 of the formation and retention of the plasma covers the working chamber 1 and penetrates into it by fields and particle flows. A controlled source of 9 neutrons can be introduced inside the reactor. Outside the working chamber, additional focal regions 11 with devices for using excess neutrons can be placed. The device 5 energy removal-energy conversion can be connected to the magnetic coils of the node forming and holding the plasma.

The method of controlled thermonuclear fusion, including the preparation, introduction and heating of a fuel mixture containing deuterium and tritium to the temperatures of nuclear interaction, plasma confinement and energy conversion, consists in adding substances that interact with positive energy release neutrons to form the initial fuel mixture tritium as a result of synthesis reactions, for example, ³ He, ⁶ Li. The mixture is introduced into the region with a high neutron density, where it is heated in the course of reactions to thermonuclear temperatures. Then, the fast neutrons are generated in a hot plasma due to nuclear fusion reactions (D + D), (D + T) in the plasma confinement region 12 inside the thermalization device 7 and the formation of a directed neutron flux due to reflections from its surfaces and form a flow of moving in selected neutron directions. As a result of this, the structures of the thermalization device and the formation of a directed neutron flux inside the reactor form focal regions with a high neutron density into which the fuel mixture is again introduced. The tritium and helium-3 nuclei formed in the nuclear reactions occurring in the reactor, after energy removal-energy conversion of the energy released in the process, are extracted from the reaction products, and subsequently included in the fuel mixture and reintroduced into the reactor.

It is essential that in the described method burnable within the focus region 8 (catalysis) of the core ³ is not compensated at the expense of their production in main syntheses, and burn-in region 12 hold core plasma ³ H replenish due to their birth in neutron nuclear reactions with ³ Not and ⁶ Li. At the same time, a (D + D) subcycle coexists in which ³ He, T nuclei are born and burned, as well as a (D + T) subcycle in which tritium nuclei are burned.

When implementing the method, a catalytically closed cycle of the device’s operation, which is self-stabilized by T and ³ He, is important (see Fig. 2). It is important that the full cycle is neutron redundant. One of the three neutrons born in the cycle should burn out, which reduces the requirements for the quality factor of the thermalization device and the formation of a directed neutron flux, and in the limit, by absorbing excess neutrons with light hydrogen isotopes, partially close the cycle by deuterium as well.

When implementing the method in the described process, ³ He, ⁶ Li, ⁷ Li reactions also occur with D and T nuclei, and a more detailed analysis should take into account their interaction, but they do not significantly affect the catalytic closure of the method cycle (see table).

It is possible to include in the initial fuel mixture isotopes ⁷ Be, ¹⁰ B, etc., not containing tritium among the reaction products, but since in these cases among the products of their interaction there are ⁶ Li and ⁷ Li isotopes containing tritium among the products of their reactions with neutrons, this is only a modification of the proposed method. The use of ⁷ Be is limited by its short lifetime.

 When implementing the method, the presence of a stationary mode, catalytically closed by all the isotopes involved in the process, is essential for its implementation. This mode is characterized by the fact that for every four interacting deuterium nuclei in the cycle, one helium-3 core interacting with neutrons is introduced into the fuel mixture.

The regime of stationary plasma burn-out catalytically closed for all participating isotopes can also be represented as a regime when the following relationship between the parameters (see Example 5) characterizing the plasma is fulfilled:
n _D · <σ · V> _DD ≥ n _T · <σ · V> _DT .

 Moreover, the number of tritium nuclei and helium-3 nuclei that are born and burn out during the implementation of the method is constant, and the method is catalytically closed by these isotopes. The method will be implemented even when it is not catalytically closed, but at the same time either the isotopes of these isotopes will be continuously produced, or their input is needed.

 A possible implementation of the method, characterized in that the fuel mixture is carried out and introduced in the form of solid targets, the neutrons are focused in the focal region at a distance from its center such that the distribution of neutron density in the focal region has a minimum at the center, and the nearest maxima lie at a distance larger targets. This makes it possible to self-center them due to inhomogeneous burning of targets in the focal region, while increasing the retention and burning time of the target.

The main thing that distinguishes the proposed method for generating energy in a controlled fusion reactor of deuterium and tritium is that the heating of the initial reaction mixture is not "external" (by introducing energy into the heated volume), but "internal" due to exothermic reactions of the interaction of the nuclei of the heated mixtures with neutrons. In this case, both in the heating region (focus) and in the region of burnout (synthesis) (the region may spatially coincide), the energy balance is positive. When organizing a closed neutron motion using the retarding-focusing structure, the method is energetically favorable, and when separating T, ³ He isotopes, and returning them to the original mixture is not limited by the raw material base. The nuclei of T and ³ He, fading, self-renew in the cycle of the method.

 The controlled thermonuclear fusion reactor operates as follows.

Fast neutrons born in the reactor, entering the device 7 of thermalization and the formation of a directed neutron flux, move in the substance of the anisotropic moderator and give it their energy, which is removed from the structure by the coolant flow. Thermalized neutrons that have lost their energy diffuse in the material of the structure, scattering on the nuclei of the moderator and controllably reflected from the surfaces of the anisotropic structure, form a neutron flux directed to the focal regions 8. At the same time, the fuel mixture input unit 4 sends a fuel mixture to the focal region 8, which contains ³ He and (or) ⁶ Li cores, as well as D and T. In order for the interaction length l _{n to} be of the order of (or shorter) sizes of the focal region 8, it is necessary that the fuel mixture enter this region either in solid or liquid, or in a gaseous state with P _He-3 ≥10 ^-2 atm (l _n ≅ 1cm). As a result of exothermic reactions of the neutron flux with ³ He and ⁶ Li nuclei, an internal heating of the mixture occurs in the part of the focal region in the catalysis region. Born in the synthesis region 12, fast neutrons are thermalized in the thermalization device 7 and the formation of a directed neutron flux and returned to the focal region 8 of the device. The neutron life cycle repeats.

 The external neutron source 9 can be made in the form of a device that implements the generation of a neutron flux due to the occurrence of nuclear reactions resulting in the formation of neutrons, for example, (α, n or γ, n), or fission reactions, and is only necessary to initiate the process .

 The reactor can operate without an external neutron source with plasma heating, as in conventional thermonuclear reactors, with external energy sources at the initial stage of operation of the device until the initiation of primary fast neutrons in the plasma.

 In additional focal areas 11, devices for using excess neutrons can be placed. This may be, for example, a device for producing deuterium from "light water" by pumping it through the additional focus area of the thermalization device 7 and forming a directed neutron flux or other devices for producing isotopes of substances.

 Using a neutron-reflecting super-mirror with ferromagnetic reflecting coatings in the device for thermalizing and generating a directed neutron flux, it is possible to control the neutron flux into the foci and additional PFS foci by changing the external magnetic field and thereby additional control of the operation of neutron sources and devices for using excess neutrons.

The device 6 for the separation of reaction products releases reaction products, primarily deuterium, tritium, helium-3, as well as substances that are not involved in the catalytic cycle of ³ He and H atoms, for their output. The separation of these substances can be carried out by any known method, for example, sorption and low-temperature separation.

The fuel mixture preparation unit 3 can be made by anyone, for example, in the form of a mixer and compressor for a working substance in the gas or liquid phases or as an external device for the manufacture of solid targets, for example, from lithium deuteride, or in the form of hollow spherical targets containing D, T, ³ He, ⁶ Li, ⁷ Li ( ⁷ Be, ¹⁰ B).

 The fuel mixture input unit 4 can be made in the form of any injector, for example, in the form of a jet nozzle for gas or liquid, or in the form of a firing device for solid targets.

The nodes 3 and 4 of the preparation and input of the working substance together with the device 6 for separating the reaction products in the controlled fusion reactor provide the necessary mode of operation of the reactor and the catalytic isolation of the ³ He and T process, controlling their composition at the reactor inlet and changing their composition after withdrawal from working chamber 1.

 Node 2 formation and retention of hot thermonuclear plasma can be any. It can be made, for example, in the form of magnetic insulating traps with a closed magnetic field, can be made with a field of open configurations of traps.

The device 5 energy removal-energy conversion, as in the prototype, primarily contains a system for removing the released energy of fast reaction products in the reactor from both charged and neutral particles on the structural elements of the reactor, including energy removal from the device for generating and focusing the thermal neutron flux, from thermalizable in fast neutrons. Additionally, the coolant is the working substance of the energy removal-energy conversion system through the coolant circuit 10 is pumped through the working chamber 1 of the reactor to remove the energy released there. As a heat carrier, it is necessary to use substances with a small neutron capture cross section that are not aggressive at their temperature destruction, for example ¹⁵ N ₂ , ⁴ He, and the use of ⁴ He in the reactor’s working chamber is most justified, although due to the temperature destruction of ¹⁵ N _{2 the} energy is taken from plasma using it is more effective.

 The heat removal circuit 10 has an energy removal-energy conversion device 5, which can be either a heat exchanger connected to a heat engine for converting heat energy into other types, for example, electrical energy, or a device for directly converting heat energy into electrical energy, for example, an MHD or EHD generator . Before entering the direct energy conversion device, there may be an energy conversion device made in the form of a nozzle, for example magnetic, which converts the thermal energy of the working substance into its longitudinal motion. In this case, an interesting option (see Fig. 4) is the implementation of the device with the plasma retention system 2, made in the form of an open magnetic trap. Hot plasma and heat carrier through the open part of the magnetic trap exit into the region of their expansion, the magnetic field in which also expands and is made in the form of a magnetic nozzle. The “internal” heating of the fuel mixture and the requirements for a high density of the substance significantly change the requirements for the working pressure inside the chamber. This is no longer a requirement for low pressure inside the chamber. The coolant can and should be pumped through the working volume of the device, which immediately reduces thermal loads on the inner wall of the device. In the process, the plasma cord flows around the coolant of circuit 10, which, cooling the peripheral region, removing energy from the surface of the plasma, neutralizing its external particles, breaks off its radial drift and makes it possible for the device to operate continuously. In addition, just as this occurs in microwave plasmatrons, the tangential swirl of the coolant flow additionally stabilizes the plasma at the axis of the trap.

 Losses of matter and energy at the periphery of the synthesis region are compensated by injection of hot plasma into it by injection of the initial fuel mixture into the focal region 8 of the thermalization device 7 and the formation of a directed flux of thermalized neutrons and self-heating of the injected mixture in neutron-nuclear reactions (see examples 4 and 5).

 It is also possible that the heat removal circuit 10 is broken, and the energy conversion device is made in the form of a nozzle, for example magnetic, that converts the thermal energy of the working substance into motion. It can be used as a jet propulsion.

It is necessary to pay attention to the fact that the cross section for the interaction of neutrons with matter increases with decreasing energy of the interaction of particles, and the length of the interaction of neutrons l _n 1 / n · σ depends on the density of these nuclei in the substance of the fuel mixture. Therefore, in the focal region 8, it is necessary either to create conditions in which the density of the fuel mixture was preserved (or increased), or fast particles produced as a result of neutron heating should leave the catalytic heating region to the burnout region, keeping the catalytic heating region 8 cold and dense. To this end, when the fuel mixture is introduced in the gas phase, the catalysis region 8 (the region of focusing of neutrons in plasma heating in the reactions of isotope-neutron interaction and the production of fast tritium nuclei) is placed in a strong magnetic field that decreases in the direction of the magnetic trap (plasma confinement region). Therefore, fast charged particles (hot plasma) appearing in exothermic neutron-nuclear reactions are “thrown” into the confinement region 12 with a magnetic field gradient and detached from the relatively cold, dense injected substance of the fuel mixture.

 The implementation of the reactor in the case where the injected fuel mixture has the form of targets that are periodically introduced into the focus area 8, allows you to implement a mode of operation similar to the operation of laser inertial installations (example 5).

At a sufficiently high injection rate (V ≥10 ⁵ cm / s), the injected substance hardly interacts with the plasma of the reactor and heats up only when interacting with neutrons in the focal regions to thermonuclear temperatures.

 The implementation of the reactor so that the distribution of the neutron density had a minimum in the center of the focus, for example, by reducing the neutron flux to some spherical surface near the focus with the surface dimensions slightly larger than the target, allows the target to self-center during burnout (Fig. 7.8). In this case, the focal region can additionally be in the field of the magnetic trap of the reactor, which makes it possible to burn off the plasma leaving this inertial-confining region to the magnetically confining region of the reactor.

 If the reactor’s operating period is shorter than the neutron extinction time in the device for generating a directed neutron flux (Example 5), then at the moment of fuel injection into neutron foci it interacts with neutrons generated in previous synthesis events in a hot plasma (Fig. 9), even if the synthesis process is interrupted periodically with a small confining field.

 In this case, we especially note the embodiment of the plasma confinement system 2 with magnetic traps 12, which contain magnetic coils that are connected to the energy removal-energy conversion device 5, and the magnetic field is periodic. In this case, due to the diamagnetic nature of the plasma, the released energy during plasma expansion is induced in the magnetic plasma confinement system into a current, which can be transferred to the payload through the power supply loop of the power removal-energy conversion system and then, for example, through a communication transformer.

 An interesting embodiment of the reactor is when the period of change in the magnetic field and current in the circuit is resonant for a given circuit, and the quality factor of the circuit is high.

 When performing the internal surfaces of the device 7 thermalization and the formation of a flux of thermalized neutrons in the form of super mirrors, with ferromagnetic coatings due to the dependence of the reflection coefficient of the mirrors on the magnitude of the magnetic field, the neutron flux in the direction of the foci is periodic with a periodic external magnetic field of the device.

 PRI me R 1. There are various options for the implementation of the node 2 of the formation and retention of hot fusion plasma in a controlled fusion reactor. It can be made in the form of various magnetic traps (Fig. 5, 6), for example, on the basis of a closed magnetic trap of the “corrugated torus” type with axial heating of the plasma, on the basis of an open trap “brakes” with peripheral heating of the plasma, etc.

 The implementation of the reactor with a closed magnetic trap that holds the hot thermonuclear plasma, when the magnetic field of the plasma formation and confinement system is closed and toroidal, allows holding significant volumes of plasma for a sufficiently long time. Considerable successes have now been achieved in matters of plasma stabilization in magnetic traps. The lifetime of hot plasma particles is mainly determined by the speed of turbulent diffusion of its particles across the magnetic field. The region 8 of the foci of the device for the formation of a directed flux of thermalized neutrons (PFS) can be placed in a strong magnetic field that decreases in the direction of the region 12 of the plasma confinement. Therefore, the fast charged particles appearing in exothermic neutron-nuclear reactions, the appearing hot plasma, are “thrown” into the trap by the gradient of the magnetic field, detached from the relatively cold, dense injected substance of the fuel mixture. In this case, the region of a strong field (together with the focus of the ZFS) can be made on the axis of the torus in the form of a constriction in an annular (azimuthal) magnetic field, which is interesting for closed traps of the "corrugated torus" type, as well as the "stellator" and "torsatron" with additional by “pulling” coils and disturbed field constancy along the azimuth and torus axis. For devices of the “tormak”, “topolotron” type, characterized by the presence of a strong transverse magnetic field decreasing in the direction of the magnetic trap (axis of the confinement region) and a pronounced field maximum at the periphery of the plasma cord, the heating region (catalysis region) and ZFS foci can be placed on the periphery. For all magnetic confinement devices, in particular tokamak-type devices, characterized by a periodic operation, the absence of a pronounced gradient of the transverse axis of the plasma cord of the magnetic field towards the axis of the cord, the essentiality of the induced current along the plasma cord, and therefore not allowing magnetic constrictions on the cord, it is possible to carry out a reactor when the PFS foci are placed inside the confinement region but are not highlighted by the maximum magnetic field, and the fuel is injected in the form of solid targets.

 Example 2. A reactor with a magnetic system 2 for forming and holding a plasma made “open” such that the focus area of the PFS coincides spatially with the maximum of the magnetic field located between the holding regions (magnetic traps), and the energy conversion devices are placed opposite the open ones the ends of the magnetic traps can be performed with the magnetic field of the traps as a "baseball" and "bottle" configuration (figure 4).

 The design of the reactor so that the magnetic system 2 of the formation and confinement of the plasma is open when the focal region 8 is in a region with a non-zero magnetic field gradient directed inside the confinement (trap) region, and an expanding nozzle, a magnetic field, is placed on the side of the "open" end of the magnetic trap which is also expanding, it is interesting to use the device as a jet engine. The operation of the device is no different from the operation of a device based on a "two-sided" open magnetic trap. The flow of the working substance can be directed both along and across the magnetic field from the side of the "closed" end of the magnetic trap.

Example 3. Considering a retardation-focusing structure (ZFS), characterized primarily as a medium with sharply distinguished anisotropy of the retardant and internal surface conductivity for neutrons selected by the structure with the possibility of geometric focusing of neutron fluxes in the focal regions of the structure, we can estimate the velocity neutron selection as an element of the structure as
(dn / d τ _out = K _w · K _v · K _{t ·} n / τ _s , where n is the density of thermal neutrons in the medium;
τ _s , time between neutron collisions with the substance of the medium;
τ _s l _s / V _n , where l _s is the mean free path of neutrons in the PFS medium,
l _s 1 / (n _s · σ _s ), where n _{s is the} density of the moderator substance;
σ _s is the neutron scattering cross section for matter;
V _{n is the} speed of thermal neutrons;
V _n 2.2 · 10 ⁵ cm / s;
K _w neutron capture efficiency in the corners;
K _w ω / 4 π where π 3,1416;
ω is the region (angular) of neutron capture by a selective structure;
K _v volumetric efficiency of neutron capture;
To _v > l _s · Φ _s / h, where h is the inter-channel distance in the selection region;
To _{t is the} efficiency of neutron transport in channels by multiple reflection of dipping neutrons by their surface.

Φ_s/π, где Φ угол между направлением осей каналов селекции и направлением движения захваченного нейтрона;
Φ < Φ_s где Φ_s угол полного отражения нейтронов поверхностью каналов.For linear structures (structures with closely spaced linear selection channels)
K _w

Φ _s / π, where Φ is the angle between the direction of the axes of the selection channels and the direction of motion of the captured neutron;
Φ <Φ _s where Φ _{s is the} angle of total neutron reflection by the channel surface.

Φ_s/π, где Φ угол между направлением движения захваченного нейтрона и плоскостью элемента структуры:
Φ < Φ_s, где Φ_s угол полного отражения нейтронов поверхностью каналов.For planar structures (structures with closely spaced planes and neutron selection channels between them
K _w

Φ _s / π, where Φ is the angle between the direction of motion of the captured neutron and the plane of the structure element:
Φ <Φ _s , where Φ _{s is the} angle of total neutron reflection by the channel surface.

For neutrons captured by the structure, K _t → 1. Hence (dn / dτ) _out K _w · K _v · K _t · n · V _n / l _s .

In the selection region along the length of the channels dx with a cross section of the selection region S, the total flow is
(dN / dτ) _out (K _w · K _v · K _t · n · V _n / l _s ) · S · dx.

This relation can be written in terms of the flux density of the neutrons selected by an element of the neutron structure dn ₂
(dN / dτ) _out S V _n dn ₂ . Hence dn ₂ n (K _w · K _v · K _t / l _s ) · dx.

We introduce the τ _full characteristic time of neutron loss by an element of the structure:
τ _full 1 / (1 / τ _out + 1 / τ _a + 1 / τ _n )
The characteristic time of neutron selection by structural elements can be estimated as
τ _out τ _s / (K _w · K _v · K _t ): where τ _out ≈ 10 ^-2 s;
τ _s ≈ 10 ^-5 s.

τ _{a the} time of absorption of neutrons by the substance ZFS:
τ _a l _a / V _n , where l _{a the} mean free path of neutrons in the PFS medium:
l _a 1 / (n _s · σ _a ), where n _{s is the} density of the moderator substance;
σ _a is the neutron absorption cross section for matter.

τ _n neutron lifetime;
τ _n 898.16 s.

Maximum number of passes by focus neutrons
N _f τ _full / τ _a .

Let us introduce to evaluate the characteristics of the structure, the number of collisions of neutrons with nuclei of matter before selection N _out .

N _out 1 / (K _w · K _v · K _t ).

To define _a coefficient selection neutrons;
K _a (dN / d τ) _out / (dN / d τ) _abs ;
K _a τ _a / τ _out;
K _a (σ _s / σ _a ) · K _w · K _t;
K _a N _s · K _w · K _t;
K _a Ns / N _out ;
(dN / d τ) _abs the neutron absorption rate by a substance;
N _{s the} number (maximum) of neutron collisions with the substance of the structure:
N _s (σ _s / σ _a )
To characterize the PFS, it is useful to introduce a coefficient of the efficiency of neutron removal by
K _eff (dN / dτ) _out (dN / dτ) _full ;
K _eff 1 / (1 + 1 / K _a · (1 + τ _a / τ _n ));
(dN / dτ) _full rate of neutron removal by matter.

It can be seen that in structures in which К _а >> 1, К _еff → 1.

By analogy with the diffusion length L, which characterizes the measure of displacement of thermal neutrons in the process of their diffusion,
L (D · τ _a ) ^1/2 (l _s · l _a / 3) ^1/2 l _s · (N _s / 3) ^1/2 you can enter the diffusion length of thermal neutrons in the process of selection
L _out (D · τ _out ) ^1/2 l _s · (N _out / 3) ^1/2 L · (1 / K _a ) ^1/2 .

In an effective ZFS, L _out <L.

It can be seen that in a structure with PFS, the neutron yield, if they were thermalized in its depth, is no longer determined by their diffuse output, but by their selective channel output. Moreover, since L _out is the diffusion length of neutrons, but in a structure with PFS, and since L _out <L, the flux of purely diffuse neutrons in comparison with a block of the same moderating substance and the same size from the surface should drop sharply.

Assuming for example that inside a constant constant in the PFS parameters, neutrons, having a density n _o at the maximum, decrease linearly to the boundary, we find the neutron density in the stream exiting the structure with a thickness L _o (with a selection channel length L _o ) with channels perpendicular to this tube selection section S,
n ₂ (n _o / 2) · K _w · K _v · K _t · (L _o / l _s )
For comparison, the flux of diffuse neutrons from the same surface with a similar distribution of neutrons in the moderator is
n ₁ 2 · n _o · (l _s / L _o ).

From here
n ₂ / n ₁ = (K _w · K _v · K _t / 4) · (L _o / l _s ) = (1/12) · (L _o / L _out ) ² .

Isotopes of substances are known for which the value of N _s is large and reaches the values of N _s ( ¹⁶ 0) 1.9 · 10 ⁴ ; N _s ( ¹⁵ N) 1.9 · 10 ⁵ ; N _s ( ²⁰⁸ Pb) 1.9 · 10 ⁵ ; N _s ( ¹³ C)
3 · 10 ³ ; N _s ( ¹⁴ C) = 5 · 10 ⁶ , based on, for example, chemical compounds of which it is possible to create structures that effectively use the mechanism of selective removal of thermal neutrons from the depth of the moderator at L _o >> l _s and at small values of L _out .

Since the flux of neutrons emanating from the PFS has a small angular divergence, when the structure is formed appropriately, the fluxes can be reduced and integrated in some selected areas called structure foci. In the simplest cases of spherical and cylindrical symmetries of devices, the density gain efficiency in converging flows can be estimated as
n (r) = n (R _in ) (R _in / r) ^k n (R _in ) · (1 / Φ _s ) ^k , where R _{in is the} internal radius (size) of the PFS;
k 1 for cylindrical structures,
k 2 for spherical structures;
For focal areas
n _f n ₂ · (1 / Φ _s ) ² for point focus or
n _f n ₂ · (1 / Φ _s ) for linear focus.

Therefore, the neutron density in the focal region at the point region of the focus can be estimated as
n _f (3 · n _o / 2) · (l _s / L _out ) ² · (L _o / l _s ) · (1 / Φ _s ) ² or with a linear focus area of the ZFS
n _f (3 · n _o / 2) · (l _s / L _out ) ² · (L _o / l _s ) · (1 / Φ _s ).

 It is seen that it is possible to increase the neutron density in a moving (converging) neutron flux in comparison with the neutron density in the moderator body.

Consider an example of a specific implementation of the device. Let the execution structure of ²⁰⁸ Pb. Then σ _s = 11.6 bn, σ _a = 4.9 · 10 ^-4 bn, N _s 2.4 · 10 ⁴ , n _s 3.3 · 10 ²² cm ^-3 , l _s 2.6 cm, L 240 cm

Suppose that the structure is characterized by the following quantities: K _t 1, h 0.1 cm, Φ = 8 ', then in the structure K _w 9.2 · 10 ^-4 , K _v 0.1. Therefore, in this case, N _out 1.4 · 10 ⁴ , L _out 170 cm, K _a 2, K _eff 0.65.

In a structure with a super-mirror coating of the channels, Φ _s = 1 ^{о is} possible; therefore, N _out 400, L _out 30 cm, K _v 0.5, K _w 5 · 10 ^-3 , K _a 60, K _eff = 0.98 (but in in this case, estimates are made without taking into account the absorption of neutrons by the coating).

The dimensions of the focal region can be estimated as
r _f R _in · Φ _s
At R _in 50 cm; Φ _s = 10 'r _f 0.15 cm, and at R _in 50 cm; Φ _s 1 ^о r _f 0.9 cm.

In this case, the neutron density at the focus is n _f 6 · n _o and n _f 25 · n _o for the cylindrical focus and n _f 2500 · n _o and n _f 1400 · n _o for the point focus, respectively, for different coatings, i.e. . n _f >> n _o .

 Moreover, in an embodiment of a structure with a varying curvature of the elements, the actual neutron density in the focus can be even higher, and the sizes of the focal region are even smaller.

 Using the proposed method and device, an increase in the energy efficiency of thermonuclear fusion is achieved due to the energetically advantageous "internal" heating of the fuel mixture when interacting with thermal neutrons, due to thermalization, return and useful use of the generated fast neutrons, and the process’s self-sufficiency in the rare isotopes used in the method and device and improving energy efficiency.

Example 4. First of all, it is necessary to pay attention to the fact that T and ³ are not rare isotopes, therefore, the cycle of an energy reactor should be catalytically closed, i.e. so that in the cycle of the reactor, their number is not reduced. Let us analyze the operation of a catalytically closed thermonuclear reactor, using the following model. Inside the reactor, thermonuclear reactions occur in a region of volume V. Neutrons generated in the reactor by the action of PFS return to focus in a certain volume V _f (they can pass this volume several times, each time returned by PFS back). The fuel mixture, including D, T, ³ He, ⁶ Li, passes through this volume, interacting with neutrons. ³ He, ⁶ Li heat the whole mixture, give rise to fast tritium nuclei. The heated plasma is captured by the magnetic field of the trap. It is believed that, on average, catalytic heating occurs only in part V _to volume V _f . The condition for the equality of burnable and generated T nuclei in the full cycle, taking into account their return to the input after removal of the released energy, provided that the T nuclei are generated both in the catalysis region V _k and in the burnup volume V.

Одновременно участвующий в процессе катализа ³Не как выгорает, так и рождается вновь:
N

N $\genfrac{}{}{0ex}{}{\text{2}}{\text{D}}$ •<σ•v>_D-D•V•τ=N

N_n•<σ•v>

V•τ=N

.

At the same time participating in the process of catalysis ³ Not both burns out and is born again:
N

N $\genfrac{}{}{0ex}{}{\text{2}}{\text{D}}$ • <σ • v> _DD • V • τ = N

N _n • <σ • v>

V • τ = N

.

N_D

Из этого условия можно найти соотношение между энерговыделением в основном объеме V и в объеме V_к от заряженных частиц в плазму в каталитически связанных D-D и ³Не-n реакциях
W

=W

W_D-D

≈ W_D-D•0,3.Therefore, the neutron density necessary for self-stabilization of ³ He,
N _n

N _D

From this condition, one can find the relationship between the energy release in the main volume V and in the volume V _k from charged particles to plasma in catalytically coupled DD and ³ He-n reactions
W

= W

W _DD

≈ W _DD • 0.3.

1 +

1+A.Comparing the conditions of self-stabilization of ³ He and T, we obtain the condition for the catalytic closure of the cycle:

1 +

1 + A.

характеризует долю энерговыделения от ⁶Li в фокусе ЗФС или с точки зрения энерговыделения
W_D-T=W

(1+A)≈3,82•W_D-D•(1+A).Here
A

characterizes the share of energy release from ⁶ Li in the focus of the ZFS or from the point of view of energy release
W _DT = W

(1 + A) ≈ 3.82 • W _DD • (1 + A).

1 +

(1+A)

, поэтому связь между энерговыделением в фокусе и области синтеза

где W_ф W_Li-n + W_He-n- энерговыделение в фокусе реактора, W_ф/W ≈ 0,129 при А 0. Относительное энерговыделение в фокусе реактора в замкнутом цикле значительно при его относительно малых размерах, может быть повышено увеличением доли ⁶Li в смеси и может быть уменьшено при неполном выжигании ядер ³Не, рожденных в цикле. В цикле, самостабилизированном по ³Не и Т, существует избыточность по нейтронам.Total energy in synthesis
W = W _DD + W _DT ≈W

1 +

(1 + A)

, therefore, the relationship between the energy release in focus and the synthesis region

where W _f W _Li-n + W _He-n is the energy release at the focus of the reactor, W _f / W ≈ 0.129 at A 0. The relative energy release at the focus of the reactor in a closed loop is significant when it is relatively small, can be increased by increasing the proportion of ⁶ Li in the mixture and can be reduced by incomplete burning of ³ He nuclei born in the cycle. In a cycle self-stabilized by ³ He and T, there is neutron redundancy.

где Ф_n (1/c) выход нейтронов из области синтеза реактора:
Ф_n (1/2 ·n $\genfrac{}{}{0ex}{}{\text{2}}{\text{D}}$ ·< σ ·V>_D-D + n_D ·n _Tx x< σ ·V>_D-T)· V (3/2 + A)· n $\genfrac{}{}{0ex}{}{\text{2}}{\text{D}}$ · < σ · V>_D-D ·V;
K_eff эффективность селекции нейтронов в ЗФС, примем K_eff 0,98;
K_t потеря нейтронов при транспортировке в ЗФС, примем K_t ≈1;
K_n число проходов нейтронами фокуса 1≅ K_n ≅К_а, 2 ≅ К_а ≅ 60.We find the neutron density in the focal region of the PFS. Using the relations characterizing the PFS, this density can be roughly estimated as
n _out (0) = f

where f _n (1 / c) the neutron yield from the synthesis of the reactor:
F _n (1/2 $\genfrac{}{}{0ex}{}{\text{2}}{\text{D}}$ Σ <σ V V> _DD + n _D <n _T x x <σ V V> _DT ) V V (3/2 + A) n n $\genfrac{}{}{0ex}{}{\text{2}}{\text{D}}$ <Σ · V> _DD · V;
K _{eff the} efficiency of neutron selection in the PFS, we will take K _eff 0.98;
K _{t the} loss of neutrons during transportation to the PFS, we take K _t ≈1;
K _{n the} number of focus neutron passes 1 ≅ K _n ≅K _a , 2 ≅ K _a ≅ 60.

Take K _n 30 (determined by the capture of neutrons in focus),
V _n 2.2 · 10 ⁵ cm / s thermal neutron velocity,
r _{f the} radius of the focal region, we take it equal to 1 cm

Поскольку в случае магнитного удержания n_D ≅ 10¹⁵ cм^-3 и < σ ·V>_D-D ≈10^-17 при Т_i ≈10⁵ эВ, то при А 0 и V ≈ 4 ·10⁶ см³ получим n_out(0) ≈ 10¹⁶ см^-3.n _out (0) = (3/2 + A) • n $\genfrac{}{}{0ex}{}{\text{2}}{\text{D}}$ • <σ • v> _DD • V

Since in the case of magnetic confinement n _D ≅ 10 ¹⁵ cm ^-3 and <σ · V> _DD ≈ 10 ^-17 at T _i ≈10 ⁵ eV, then at A 0 and V ≈ 4 · 10 ⁶ cm ³ we get n _out (0 ) ≈ 10 ¹⁶ cm ^-3 .

считая, что V_ф/V_к1. Получим n_3He ≈3· 10¹⁷ см^-3 для случая < σ ·V >_He-n ≈ 1,2 ·10^-15 см^-3/с, что эквивалентно давлению газа в струе Р_3Не(атм) 3,7 ·10^-20 n_3He (см^-3) ≈ 0,01 атм.We also find the density of ³ He in the jet of gas injected into the focus,
n

assuming that V _f / V _to 1. We get n _3He ≈3 · 10 ¹⁷ cm ^-3 for the case <σ · V> _He-n ≈ 1.2 · 10 ^-15 cm ^{-3 /} s, which is equivalent to the gas pressure in jet P _3He (atm) 3.7 · 10 ^-20 n _3He (cm ^-3 ) ≈ 0.01 atm.

For the case under consideration, WW _DD x x [(2.4 + A) / (1 + A)] 1.602 · 10 ^-19 2.43 · 10 ⁶ (10 ¹⁵ ) ² · 10 ^-17 2.4 4 · 10 ⁶ ≈ 37.3 10 ⁶ ; W 37.3 · 10 ⁶ W; W _f 2.9 · 10 ⁶ W.

W_ф/(1,602· 10^-19 ·n_3He ·r $\genfrac{}{}{0ex}{}{\text{2}}{\text{ф}}$ ·V_г)

16 ·10⁴ эВ, при этом считая, что V_r

10³ см/с и струя состоит только из ³Не. Для поперечной инжекционной струи (поперек магнитного поля) в области магнитной перетяжки, когда холодный газ проходит мимо, или при вводе вещества в виде твердых мишеней при импульсном режиме работы реактора (смотри далее) температуру инжектируемой плазмы можно увеличить. Кроме того, в пусковом режиме необходимо резко увеличить плотность нейтронов в фокусе, что можно сделать, используя каталитически не стабилизированный режим с n_D ≈ n_Т.
П р и м е р 5. Каталитический разогрев топливной термоядерной смеси возможен не только в устройствах, работающих в стационарном режиме, но и в устройствах, которые работают в импульсном режиме. Пусть имеем каталитический реактор, в котором ЗФС выполнена в виде полого шара с нейтронным фокусом в ее геометрическом центре. Пусть твердые шаровые мишени, содержащие ³Не, ⁶Li, D, T, с помощью стреляющего устройства периодически вбрасываются в область нейтронного фокуса. Тогда, если в момент когда мишень находится в фокусе структуры, ЗФС сформировала поток сходящихся к центру, движущихся с тепловыми скоростями (V_n 2,2 ·10⁵см/сек) нейтронов, то при попадании этого потока на мишень в приповерхностном слое начинается интенсивное энерговыделение в результате протекания (³Не, n) и (или) (⁶Li,n) ядерных реакций. Сделаем оценки процесса выгорания мишени. Длину взаимодействия нейтронов с веществом можно представить как l_n 1/n ·σ. Для случая холодной мишени, содержащей ядра ³Не, ⁶Li, находящиеся в фокусе структуры, и на которую с тепловой скоростью набегает плотный фронт тепловых нейтронов, поскольку σ= 5,4 ·10^-21 см² и n n_He ≈10²² см^-3, получим l_n 2 ·10^-2 см. При этом только за счет энерговыделения от нейтронных реакций температура плазмы в приповерхностной области может достичь величины

Здесь считаем, что Q_n 0,78 МэВ, n_3He/(n_3He+ n_P + n_T + n_ocн) 1/4, n

/n

1 на поверхности;
n

плотность ³Не в мишени;
n_D плотность D в мишени;
n_T плотность Т в мишени;
n_осн плотность базового вещества, в котором содержатся ³Не, Т, D;
n

плотность нейтронов на фронте.Assuming that all the energy released in focus is used to heat the gas jet, we find the temperature of the resulting plasma
T _pl

W _f / (1.602 · 10 ⁻¹⁹ · n _3He · r $\genfrac{}{}{0ex}{}{\text{2}}{\text{f}}$ V _g )

16 · 10 ⁴ eV, while assuming that V _r

10 ³ cm / s and the jet consists of only ³ He. For a transverse injection jet (across the magnetic field) in the magnetic waist region, when cold gas passes by, or when a substance is injected in the form of solid targets during a pulsed reactor operation mode (see below), the temperature of the injected plasma can be increased. In addition, in the starting mode, it is necessary to sharply increase the neutron density in focus, which can be done using a catalytically unstable mode with n _D ≈ n _T.
PRI me R 5. Catalytic heating of the fuel thermonuclear mixture is possible not only in devices operating in stationary mode, but also in devices that operate in pulsed mode. Let us have a catalytic reactor in which the PFS is made in the form of a hollow ball with a neutron focus at its geometric center. Let solid spherical targets containing ³ He, ⁶ Li, D, T, with the help of a firing device, be periodically thrown into the region of the neutron focus. Then, if at the moment when the target is in the focus of the structure, the PFS formed a flux of neutrons converging toward the center, moving with thermal velocities (V _n 2.2 · 10 ⁵ cm / s), then when this flux hits the target in the surface layer, intense energy release as a result of the occurrence of ( ³ He, n) and (or) ( ⁶ Li, n) nuclear reactions. We make estimates of the process of burning out the target. The length of the interaction of neutrons with matter can be represented as l _n 1 / n · σ. For the case of a cold target containing ³ He, ⁶ Li nuclei located at the focus of the structure, and onto which a dense front of thermal neutrons runs at a thermal speed, since σ = 5.4 · 10 ^-21 cm ² and nn _He ≈10 ²² cm ^{- 3} , we obtain l _n 2 · 10 ^-2 cm. Moreover, only due to energy release from neutron reactions the plasma temperature in the near-surface region can reach

Here we assume that Q _n 0.78 MeV, n _3He / (n _3He + n _P + n _T + n _ocн ) 1/4, n

/ n

1 on the surface;
n

density ³ Not in the target;
n _{D is the} density D in the target;
n _{T is the} density T in the target;
n _basic density of the base substance, which contains ³ He, T, D;
n

neutron density at the front.

/ n

≈ 0,1.If the target surface consists of lithium deuteride saturated with tritium, then T _pl 0.2 MeV at n

/ n

≈ 0.1.

наружу протекает горячая плазма, содержащая ³Не (⁶Li). Длина выгорания быстрых ³Не в нейтронном фронте l_n 50 см. Степень выгорания на расстоянии Δr= 1 см

0,02 достаточно высока, важно, что при этом рождается поток горячих ядер трития (W_T 0,19 МэВ). Кроме того, в приповерхностном слое горячей плазмы протекают (D,D) и (D,T) термоядерные реакции. Плазменное давление в приповерхностном слое получим, приняв Т_ф 10⁵ эВ, n_ф 10²²см^-3, равным Р _пл 1,58· 10^-18 · n_ф · Т_ф= 10⁹ атм.The velocity of the incident neutron flux is significantly lower than the velocities of the hot ions of the burning out near-surface plasma; we can assume that through a stationary front of neutrons with density n

hot plasma containing ³ He ( ⁶ Li) flows out. The burnup length of fast ³ He in the neutron front l _n 50 cm. The degree of burnup at a distance Δr = 1 cm

0.02 is quite high, it is important that in this case a stream of hot tritium nuclei is generated (W _T 0.19 MeV). In addition, thermonuclear reactions occur in the surface layer of hot plasma (D, D) and (D, T). We obtain the plasma pressure in the surface layer by taking T _f 10 ⁵ eV, n _f 10 ²² cm ^-3 , equal to R _pl 1.58 · 10 ^-18 · n _f · T _f = 10 ⁹ atm.

Важно, что dn

+ dn_T (n $\genfrac{}{}{0ex}{}{\text{2}}{\text{D}}$ ·<σ·V>_D-D n_D ·n_T ·< σ·V>_D-T) ·d τ
Условие каталитической замкнутости процесса требует, чтобы dn

/ dτ 0; dn_T/d τ 0. Это означает, что n_D ·< σ ·V>_D-D n_T ·< σ · V>_D-T. Возможен режим работы (n_D ·< σ ·V>_D-D) > (n_T ·< σ ·V>_D-T) с наработкой Т и ³Не в реакторе. Соотношение прежде всего отражает тот факт, что основной канал рождения ³Не и Т это DD-реакции, хотя Т может и рождаться и вымирать и в других процессах (см.таблицу), которые в более полном анализе должны учитываться в уравнениях процесса. Насыщенность мишени тритием желательна только в приповерхностном слое. Время выгорания мишени можно оценить как

r_o/V

10^-9 c, но наличие скачка давления в области нейтронного фронта в результате протекающих там (³Не, n) реакций может увеличить общее время выгорания мишени. Если все же τ_i

10^-9 с, то эту эффективность можно оценить как k_D

n_D•<σ•v>_D-D•τ_i=10^-3 при n_D 10²³ см^-3, <σ•v>_D-D

10^-15 см^-3/c. Плотность потока быстрых нейтронов из области выгорания n_nm ≈ 3/2n $\genfrac{}{}{0ex}{}{\text{2}}{\text{D}}$ · < σ · V>_D-D· τ_i ≈ 10²¹ cм^-3.A shock wave should appear on the target surface n >> n _o 10 ²² cm ^-3 . The density of fast neutrons generated in the combustion region is estimated as n _nf (1/2 n $\genfrac{}{}{0ex}{}{\text{2}}{\text{D}}$ <Σ · V> _DD + n _D · n _T <σ · V> _DT ) · l _n / V _i for V _i 10 ³ cm / s, <σ · V> ≈10 ^-15 cm ³ / s, l _n ≈ 10 ^-2 cm; n _nf 10 ¹⁹ cm ^-3 with n _D n _T 10 ²² cm ^-3 ; n _nf
10 ²¹ cm ^-3 for n _D n _T 10 ²³ cm ^-3 . A neutron field of this density, moving at a speed of V _n 10 ⁸ cm / s, penetrates the whole body of the target in a time τ ≈ 10 ^-10 s and its intense heating begins during ( ³ He, n) reactions and fast tritium nuclei. Its explosive burnout begins. In the process of combustion reactions in the target volume, the following basic kinetic equations are fulfilled (without taking into account the high-temperature combustion channels of the T and ³ He isotopes):

It is important that dn

+ dn _T (n $\genfrac{}{}{0ex}{}{\text{2}}{\text{D}}$ <Σ · V> _DD n _D · n _T · <σ · V> _DT ) d d
The condition of catalytic isolation of the process requires that dn

/ dτ 0; dn _T / d τ 0. This means that n _D · <σ · V> _DD n _T · <σ · V> _DT . The operating mode (n _D · <σ · V> _DD )> (n _T · <σ · V> _DT ) with an operating time of T and ³ He in the reactor is possible. The correlation primarily reflects the fact that the main channel for the production of ³ He and T is a DD reaction, although T can be born and die out in other processes (see table), which should be taken into account in the process equations in a more complete analysis. Saturation of the target with tritium is desirable only in the surface layer. Target burnup time can be estimated as

r _o / V

10 ^-9 s, but the presence of a pressure jump in the region of the neutron front as a result of the reactions occurring there ( ³ He, n) can increase the total time of the burnout of the target. If nevertheless τ _i

10 ^-9 s, then this efficiency can be estimated as k _D

n _D • <σ • v> _DD • τ _i = 10 ^-3 for n _D 10 ²³ cm ^-3 , <σ • v> _DD

10 ^-15 cm ^-3 / s. Fast neutron flux density from the burnup region n _nm ≈ 3 / 2n $\genfrac{}{}{0ex}{}{\text{2}}{\text{D}}$ · <Σ · V> _{DD ·} τ _i ≈ 10 ²¹ cm ^-3 .

/2π.Fast neutrons born in the process of burning out enter the spherical ZFS at a speed of V _n 10 ⁹ cm / s, during time τ≈ τ _i ≈ 10 ^-5 s they slow down to thermal speeds, giving their energy to the structure. Then the PFS returns thermal neutrons back to the region of the neutron focus. In this case, neutrons returning from the deceleration region from the radius RR _in + L at R 2 · 10 ² cm reach the focus of the structure in a time τ R _n / V _n ≈ 10 ^-3 s. (R _{in is the} inner radius of the PFS; L _s is the neutron moderation length). Neutron Density at the Front of a Converging Flux
n _n = n _nm • (r _o / r)

/ 2π.

≈ 10⁴;
Δ Ω / 2 π ≈ 10^-3, то n_n ≈ 10²² см^-3.If n _nm ≈10 ²¹ cm ^-3 ; r _o / r ≈ 1;

≈ 10 ⁴ ;
Δ Ω / 2 π ≈ 10 ^-3 , then n _n ≈ 10 ²² cm ^-3 .

(n_nm•(r_o/r)

2π)•τ_full/T, где Т период изменения магнитного поля.The initial conditions are repeated. The burnout process will be repeated if, before the neutron front collapses, a new target is placed in focus. The time plot of the density of generated fast neutrons and returned slow neutrons is shown in FIG. 6. In this case, for the purpose of self-centering of a burning target during the combustion process, neutrons may not be brought into focus, but onto some spherical surface around it, an approximate distribution of neutron density in focus in this case is shown in FIG. 7. It is possible for the reactor to operate when the reflecting surfaces of the ZFS are made using ferromagnetic material, and the external magnetic field is periodic and pulsed. In this case, targets from the fuel mixture are introduced into the device with the same period, and the neutron density at the front of the converging stream, if the period of the field change is less than the neutron extinction time in the PFS T << τ _full , can reach
n _n

(n _nm • (r _o / r)

2π) • τ _full / T, where T is the period of change of the magnetic field.

Claims (9)

 1. A method of controlled thermonuclear fusion, including the preparation, introduction and heating of a fuel mixture containing deuterium and tritium to nuclear interaction temperatures, plasma confinement and energy conversion, characterized in that substances interacting with neutrons with positive energy release are added to the initial fuel mixture generating tritium as a result of fusion reactions, while thermalizing the neutrons generated in fusion reactions and focusing them in the focal region on the fuel mixture when heated, and After holding the hot thermonuclear plasma and converting the released energy, tritium and helium-3 nuclei are isolated from the reaction products in the plasma and introduced into the initial fuel mixture. 2. The method according to claim 1, characterized in that the temperature in the plasma is maintained such that the following relationship between the parameters characterizing the plasma is fulfilled:
n _D • <σ • v> _DD ≥n _T • <σ • v> _DT ,
where n _D is the density of deuterium in the plasma;
n _t - plasma tritium density;
<σ • v> _DD is the average product of the interaction cross section and the ion velocity in DD reactions in the plasma;
<σ • v> _DT is the averaged product of the interaction cross section and the ion velocity in the DT reactions in the plasma.  3. The method according to claim 1, characterized in that the fuel mixture is carried out and introduced in the form of solid targets, while the neutrons are focused in the focal region at a distance from its center so that the neutron density distribution in the focal region has a minimum at the center, and the nearest the maxima lie at a distance greater than the size of the targets.  4. A controlled thermonuclear fusion reactor comprising a working chamber including a plasma forming and holding unit and a plasma holding area, a preparation unit and a fuel mixture input unit, an energy removal-energy conversion device, and a reaction product separation device, characterized in that the plasma forming unit is equipped with a thermalization device and the formation of a directed neutron flux with a focal region, while the site of the input of the fuel mixture is oriented to the focal region of the flow of the thermalization device and Bani directional neutron flux, wherein the separation of the reaction products node coupled to node producing a fuel mixture.  5. The reactor according to claim 4, characterized in that the energy removal-energy conversion device comprises a coolant circuit with channels of the coolant circuit, which is connected to the working chamber and the separation unit of the reaction products.  6. The reactor according to claim 5, characterized in that the channels of the coolant circuit at the entrance to the working chamber of the reactor have a tangential slope relative to the plasma confinement region.  7. The reactor according to claim 4, characterized in that the plasma forming and holding unit is made in the form of a magnetic trap.  8. The reactor according to claim 7, characterized in that the plasma formation and retention unit is made in the form of an open magnetic trap, part of which has the form of a magnetic nozzle connected to an energy removal-energy conversion device.  9. The reactor according to p. 7, characterized in that the magnetic trap contains magnetic coils that are connected to a device for energy extraction-energy conversion.

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